MTF BIBLIOGRAPHY
Title: MAGNETIZED TARGET FUSION - AN OVERVIEW
Author: KIRKPATRICK, RC; LINDEMUTH, IR; WARD, MS
Journal: FUSION TECHNOLOGY ; MAY 1995; v.27, no.3, p.201-214
Doc. Type: ARTICLE
Abstract: The magnetized target fusion (MTF) concept is explained, and the
underlying principles are discussed. The necessity of creating a target plasma
and the advantage of decoupling its creation from the implosion used to achieve
fusion ignition are explained. The Sandia National Laboratories Phi-target
experiments is one concrete example of the MTF concept, but other experiments
have involved some elements of MTF. Lindl-Widner diagrams are used to elucidate
the parameter space available to MTF and the physics of MTF ignition. Magnetized
target fusion has both limitations and advantages relative to inertial
confinement fusion. The chief advantage is that the driver for an MTF target can
be orders of magnitude less powerful and in tense than what is required for
other inertial fusion approaches. A number of critical issues challenge the
practical realization of MTF. Past experience, critical issues, and potential
integral MTF experiments are discussed.
Institution: LOS ALAMOS NATL LAB, POB 1663, LOS ALAMOS, NM, 87545
Times Cited: 23
Bibliography: 26
Article:
http://linkseeker.lanl.gov/lanl?genre=article&issn=0748-1896&date=1995&volume=27&issue=3&spage=201&atitle=MAGNETIZED+TARGET+FUSION+%2D+AN+OVERVIEW&aulast=KIRKPATRICK&auinit=RC
Title: A physics exploratory experiment on plasma liner formation
Author: Thio, YCF; Knapp, CE; Kirkpatrick, RC; Siemon, RE; Turchi, PJ
Journal: JOURNAL OF FUSION ENERGY; JUN 2001; v.20, no.1-2, p.1-11
Doc. Type: Article
Abstract: Momentum flux for imploding a target plasma in magnetized target
fusion (MTF) may be delivered by an array of plasma guns launching plasma jets
that would merge to form an imploding plasma shell (liner). In this paper, we
examine what would be a worthwhile experiment to explore the dynamics of merging
plasma jets to form a plasma liner as a first step in establishing an
experimental database for plasma-jets-driven magnetized target fusion (PJETS-MTF).
Using past experience in fusion energy research as a model, we envisage a
four-phase program to advance the art of PJETS-MTF to fusion breakeven (Q
similar to 1). The experiment (PLX) described in this paper serves as Phase 1 of
this four-phase program. The logic underlying the selection of the experimental
parameters is presented. The experiment consists of using 12 plasma guns
arranged in a circle, launching plasma jets toward the center of a vacuum
chamber. The velocity of the plasma jets chosen is 200 km/s, and each jet is to
carry a mass of 0.2 mg to 0.4 mg. A candidate plasma accelerator for launching
these jets consists of a coaxial plasma gun of the Marshall type.
Institution: NASA, George C Marshall Space Flight Ctr, Huntsville, AL 35812 USA;
NASA, George C Marshall Space Flight Ctr, Huntsville, AL 35812 USA; Los Alamos
Natl Lab, Los Alamos, NM 87545 USA; USAF, Res Lab, Kirtland AFB, NM 87185 USA
Times Cited: 0
Bibliography: 24
Article:
http://linkseeker.lanl.gov/lanl?genre=article&issn=0164-0313&date=2001&volume=20&issue=1-2&spage=1&atitle=A+physics+exploratory+experiment+on+plasma+liner+formation&aulast=Thio&auinit=YCF
Title: Magnetic field measurements inside a converging flux conserver for
magnetized target fusion applications
Author: Taccetti, JM; Intrator, TP; Wysocki, FJ; Forman, KC; Gale, DG; Coffey,
SK; Degnan, JH
Journal: FUSION SCIENCE AND TECHNOLOGY; JAN 2002; v.41, no.1, p.13-23
Doc. Type: Article
Abstract: Two experiments showing continuous, real-time measurements of the
radial convergence of a high-aspect-ratio aluminum flux conserver are presented.
These results were obtained by measuring the compression of both axial and
radial components of an internal low-intensity magnetic field. Repeatable flux
conserver compressions of this type, uniform to 10:1 compression ratio, form a
step toward achieving magnetized target fusion, where a plasma of appropriate
temperature and density would be introduced into the flux conserver for
compression to fusion conditions. While X radiographs show this compression
ratio was achieved, the magnetic field probe signals were cut off earlier. Axial
component measurements resulted in compression ratios of 7:1 and 6.3:1, for the
first and second compressions, before the magnetic probe signals were lost.
Radial component measurements disagree with the axial probe results. Although
the discrepancy between axial and radial probe measurements is not completely
understood, possible explanations are presented.
Institution: Los Alamos Natl Lab, POB 1663, Los Alamos, NM 87545 USA; Los Alamos
Natl Lab, Los Alamos, NM 87545 USA; Sci Applicat Int Corp, Albuquerque, NM 87106
USA; NumerEx, Albuquerque, NM 87106 USA; USAF, Res Lab, Kirtland AFB, NM 87117
USA
Times Cited: 0
Bibliography: 19
Article:
http://linkseeker.lanl.gov/lanl?genre=article&issn=0748-1896&date=2002&volume=41&issue=1&spage=13&atitle=Magnetic+field+measurements+inside+a+converging+flux+conserver+for+magnetized+target+fusion+applications&aulast=Taccetti&auinit=JM
Title: Alpha particles play a relatively minor role in magnetized target fusion
systems
Author: Ryutov, DD
Journal: FUSION SCIENCE AND TECHNOLOGY; MAR 2002; v.41, no.2, p.88-91
Doc. Type: Article
Abstract: Two problems related to alpha particle physics in magnetized target
fusion (MTF) systems are briefly discussed. First, we evaluate the pressure and
density of alpha particles under the assumption that they are perfectly confined
and have a classical slowing-down distribution. It turns out that because of a
comparatively low plasma temperature in MTF systems, the relative pressure and
density of alpha particles are more than an order of magnitude less than in
fusion reactors based on ITER-type tokamaks. Therefore, one may expect that even
in the extreme case of a perfect confinement of alpha particles, their presence
will have a much weaker (than in the case of tokamaks) effect on plasma
stability and transport. Second, we discuss the kinetics of plasma burn under
the opposite extreme assumption that all the alpha particles are instantaneously
lost, without leaving any energy in a plasma. It turns out that even in this
case, the plasma energy yield in batch-burn systems is only weakly affected by
burnout effects.
Institution: Lawrence Livermore Natl Lab, POB 808, L-630, Livermore, CA 94551
USA; Lawrence Livermore Natl Lab, Livermore, CA 94551 USA
Times Cited: 0
Bibliography: 9
Article:
http://linkseeker.lanl.gov/lanl?genre=article&issn=0748-1896&date=2002&volume=41&issue=2&spage=88&atitle=Alpha+particles+play+a+relatively+minor+role+in+magnetized+target+fusion+systems&aulast=Ryutov&auinit=DD
Title: Computational and experimental investigation of magnetized target fusion
Author: Sheehey, PT; Guzik, JA; Kirkpatrick, RC; Lindemuth, IR; Scudder, DW;
Shlachter, JS; Wysocki, FJ
Journal: FUSION TECHNOLOGY; DEC 1996; v.30, no.3, pt.2B, p.1355-1359
Doc. Type: Article
Abstract: In Magnetized Target Fusion (MTF), a preheated and magnetized target
plasma is hydrodynamically compressed to fusion conditions.(1,2) Because the
magnetic field suppresses losses by electron thermal conduction in the fuel
during the target implosion heating process, the compression may be over a much
longer time scale than in traditional inertial confinement fusion (ICF). Bigger
targets and much lower initial target densities than in ICF can be used,
reducing radiative energy losses. Therefore, ''liner-on-plasma'' compressions,
driven by relatively inexpensive electrical pulsed power, may be practical.
Potential MTF target plasmas must meet minimum temperature, density, and
magnetic field starting conditions, and must remain relatively free of high-Z
radiation-cooling-enhancing contaminants. At Los Alamos National Laboratory,
computational and experimental research is being pursued into MTF target
plasmas, such as deuterium-fiber-initiated Z-pinches,(3) and the
Russian-originated ''MACO'' plasma.(4) In addition, liner-on-plasma compressions
of such target plasmas to fusion conditions are being computationally modeled,
and experimental investigation of such heavy liner implosions has begun. The
status of the research will be presented.
Institution: LOS ALAMOS NATL LAB, POB 1663, LOS ALAMOS, NM 87545
Times Cited: 1
Bibliography: 9
Article:
http://linkseeker.lanl.gov/lanl?genre=article&issn=0748-1896&date=1996&volume=30&issue=3&spage=1355&atitle=Computational+and+experimental+investigation+of+magnetized+target+fusion&aulast=Sheehey&auinit=PT
Title: Magnetized target fusion in cylindrical geometry
Author: Basko, MM; Churazov, MD; Kemp, A; Meyer-ter-Vehn, J
Journal: NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION
A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT; MAY 21 2001;
v.464, no.1-3, p.196-200
Doc. Type: Article
Abstract: General ignition conditions for magnetized target fusion (MTF) in
cylindrical geometry are formulated. To attain an MTF ignition state, the
deuterium-tritium fuel must be compressed in the regime of self-sustained
magnetized implosion (SSMI). We analyze the general conditions and optimal
parameter values required for initiating such a regime, and demonstrate that the
SSMI regime can already be realized in cylindrical implosions driven by similar
to 100 kJ beams of fast ions. (C) 2001 Elsevier Science B.V. All rights
reserved.
Institution: Inst Theoret & Expt Phys, B Cheremushkinskaya 25, Moscow 117259,
Russia; Inst Theoret & Expt Phys, Moscow 117259, Russia; Max Planck Inst
Quantenopt, D-85748 Garching, Germany
Times Cited: 0
Bibliography: 10
Article:
http://linkseeker.lanl.gov/lanl?genre=article&issn=0168-9002&date=2001&volume=464&issue=1-3&spage=196&atitle=Magnetized+target+fusion+in+cylindrical+geometry&aulast=Basko&auinit=MM
Title: Experimental measurements of a converging flux conserver suitable for
compressing a field reversed configuration for magnetized target fusion
Author: Intrator, T; Taccetti, M; Clark, DA; Degnan, JH; Gale, D; Coffey, S;
Garcia, J; Rodriguez, P; Sommars, W; Marshall, B; Wysocki, F; Siemon, R; Faehl,
R; Forman, K; Bartlett, R; Cavazos, T; Faehl, RJ; Forman, K; Frese, MH; Fulton,
D; Gueits, JC; Hussey, TW; Kirkpatrick, R; Kiuttu, GF; Lehr, FM; Letterio, JD;
Lindemuth, I; McCullough, W; Moses, R; Peterkin, RE; Reinovsky, RE; Roderick,
NF; Ruden, EL; Schoenberg, KF; Scudder, D; Shlachter, J; Wurden, GA
Journal: NUCLEAR FUSION; FEB 2002; v.42, no.2, p.211-222
Doc. Type: Article
Abstract: Data are presented that are part of a first step in establishing the
scientific basis of magnetized target fusion (MTF) as a cost effective approach
to fusion energy. A radially converging flux compressor shell with
characteristics suitable for MTF is demonstrated to be feasible. The key
scientific and engineering question for this experiment is whether the large
radial force density required to uniformly pinch this cylindrical shell would do
so without buckling or kinking its shape. The time evolution of the shell has
been measured with several independent diagnostic methods. The uniformity,
height to diameter ratio and radial convergence are all better than required to
compress a high density field reversed configuration to fusion relevant
temperature and density.
Institution: Los Alamos Natl Lab, Los Alamos, NM 87544 USA; Los Alamos Natl Lab,
Los Alamos, NM 87544 USA; Air Force Res Lab, Kirtland AFB, NM USA; Maxwell
Technol Inc, Albuquerque, NM USA; NumerEx, Albuquerque, NM USA; Univ New Mexico,
Dept Chem & Nucl Engn, Albuquerque, NM USA; Bechtel Nevada Inc, Las Vegas, NV
USA
Times Cited: 0
Bibliography: 45
Article:
http://linkseeker.lanl.gov/lanl?genre=article&issn=0029-5515&date=2002&volume=42&issue=2&spage=211&atitle=Experimental+measurements+of+a+converging+flux+conserver+suitable+for+compressing+a+field+reversed+configuration+for+magnetized+target+fusion&aulast=Intrator&auinit=T
Title: On drift instabilities in magnetized target fusion devices
Author: Ryutov, DD
Journal: PHYSICS OF PLASMAS; SEP 2002; v.9, no.9, p.4085-4088
Doc. Type: Article
Abstract: Some versions of magnetized target fusion (MTF) devices will be using
a high beta plasma, with local beta exceeding 1. Drift instabilities in such a
plasma are electromagnetic and are quite different from the analogous
instabilities in a low beta plasma. In a collisionless limit they have been
analyzed by El Nadi and Rosenbluth [Phys. Fluids 16, 2036 (1973)] who have shown
that the cross-field transport coefficients in such a plasma may exceed a Bohm
value. On the other hand, high-density plasma in MTF systems is usually strongly
collisional in the sense that the drift frequency for the most dangerous
large-scale perturbations is smaller than the ion-ion collision frequency, and
the particle mean free path is shorter than the parallel wavelength. This regime
is studied in the present paper. It is shown that transport coefficients in the
MTF plasma are usually smaller than the Bohm diffusion coefficient. (C) 2002
American Institute of Physics.
Institution: Lawrence Livermore Natl Lab, Livermore, CA 94551 USA; Lawrence
Livermore Natl Lab, Livermore, CA 94551 USA
Times Cited: 0
Bibliography: 13
Article:
http://linkseeker.lanl.gov/lanl?genre=article&issn=1070-664x&date=2002&volume=9&issue=9&spage=4085&atitle=On+drift+instabilities+in+magnetized+target+fusion+devices&aulast=Ryutov&auinit=DD
Title: TARGET PLASMA FORMATION FOR MAGNETIC COMPRESSION MAGNETIZED TARGET FUSION
Author: LINDEMUTH, IR; REINOVSKY, RE; CHRIEN, RE; CHRISTIAN, JM; EKDAHL, CA;
GOFORTH, JH; HAIGHT, RC; IDZOREK, G; KING, NS; KIRKPATRICK, RC; LARSON, RE;
MORGAN, GL; OLINGER, BW; OONA, H; SHEEHEY, PT; SHLACHTER, JS; SMITH, RC; VEESER,
LR; WARTHEN, BJ; YOUNGER, SM; CHERNYSHEV, VK; MOKHOV, VN; DEMIN, AN; DOLIN, YN;
GARANIN, SF; IVANOV, VA; KORCHAGIN, VP; MIKHAILOV, OD; MOROZOV, IV; PAK, SV;
PAVLOVSKII, ES; SELEZNEV, NY; SKOBELEV, AN; VOLKOV, GI; YAKUBOV, VA
Journal: PHYSICAL REVIEW LETTERS ; SEP 4 1995; v.75, no.10, p.1953-1956
Doc. Type: ARTICLE
Abstract: Experimental observations of plasma behavior in a novel plasma
formation chamber are reported. Experimental results are in reasonable agreement
with two-dimensional magnetohydrodynamic computations suggesting that the plasma
could subsequently be adiabatically compressed by a magnetically driven pusher
to yield 1 GJ of fusion energy. An explosively driven helical flux compression
generator mated with a unique closing switch/opening switch combination
delivered a 2.7 MA, 347 mu s magnetization current and an additional 5 MA, 2.5
mu s electrical pulse to the chamber. A hot plasma was produced and 10(13) D-T
fusion reactions were observed.
Institution: LOS ALAMOS NATL LAB, LOS ALAMOS, NM, 87545 ALL RUSSIAN SCI RES INST
EXPTL PHYS, ARZAMAS 16, RUSSIA, EG&G ENERGY MEASUREMENTS INC, LOS ALAMOS OPERAT,
LOS ALAMOS, NM, 87545
Times Cited: 11
Bibliography: 15
Article:
http://linkseeker.lanl.gov/lanl?genre=article&issn=0031-9007&date=1995&volume=75&issue=10&spage=1953&atitle=TARGET+PLASMA+FORMATION+FOR+MAGNETIC+COMPRESSION+MAGNETIZED+TARGET+FUSION&aulast=LINDEMUTH&auinit=IR
Title: MULTIMEGAJOULE ELECTROMAGNETIC IMPLOSION OF SHAPED SOLID-DENSITY LINERS
Author: DEGNAN, JH; BAKER, WL; ALME, ML; BOYER, C; BUFF, JS; BEASON, JD; CLOUSE,
CJ; COFFEY, SK; DIETZ, D; FRESE, MH; GRAHAM, JD; HALL, DJ; HOLMES, JL; LOPEZ,
EA; PETERKIN, RE; PRICE, DW; RODERICK, NF; SEILER, SW; SOVINEC, CR; TURCHI, PJ
Journal: FUSION TECHNOLOGY ; MAR 1995; v.27, no.2, p.115-123
Doc. Type: ARTICLE
Abstract: Electromagnetic implosions of shaped cylindrical aluminum liners that
remain at solid density are discussed. The approximate liner parameters have an
initial radius of 3 to 4 cm, are 4 cm in height, and are approximately 0.1 cm
thick. The liners are driven by the Shiva Star 1300-muf capacitor bank at an
84-kV charging voltage and an approximately 30-nH total initial inductance
(including implosion load). The discharge current travels along the length of
the liner and rises to 14 MA in approximately 8 mus. The implosion time is
approximately 12 mus. Diagnostics include inductive current and capacitive
voltage probes, magnetic probes, and radiography. Both right-circular cylinder
and conical liner implosion data are displayed and discussed. Radiography
indicates implosion behavior substantially consistent with two-dimensional
magnetohydrodynamic calculations, which predict inner surface implosion
velocities exceeding 20 km/s, and compressed density of two to three times solid
density. Less growth of perturbations is evident for the conical liner
(approximately 1% thickness tolerance) than for the right-circular cylindrical
liner (approximately 3% thickness tolerance).
Institution: PHILLIPS LAB, DIV HIGH ENERGY PLASMA, KIRTLAND AFB, NM, 87117
Times Cited: 5
Bibliography: 12
Article:
http://linkseeker.lanl.gov/lanl?genre=article&issn=0748-1896&date=1995&volume=27&issue=2&spage=115&atitle=MULTIMEGAJOULE+ELECTROMAGNETIC+IMPLOSION+OF+SHAPED+SOLID%2DDENSITY+LINERS&aulast=DEGNAN&auinit=JH
Title: Energetic alpha transport in a magnetized fusion target
Author: Kirkpatrick, RC; Smitherman, DP
Journal: FUSION TECHNOLOGY; DEC 1996; v.30, no.3, pt.2B, p.1311-1314
Doc. Type: Article
Abstract: Magnetized target fusion (MTF) promises to ease the power and
intensity requirements for a fusion driver. High gain MTF targets require fusion
ignition to occur in the magnetized fuel. Ignition requires the energy deposited
by the charged fusion reaction products to exceed that lost from the plasma by a
variety of loss mechanisms. We have used single particle tracking through a
magnetized plasma to obtain preliminary results on the DT alpha particle
deposition as a function of the plasma rho R and BR for a uniform spherically
symmetric volume with a uniform B-theta magnetic field. More complicated plasma
density, temperature, and field distributions can be handled by the code,
including 2-D distributions, but the efficiency of this approach makes extensive
calculations impractical. A more efficient approach is needed, particularly for
use in dynamic calculations. However, particle tracking is useful for obtaining
information for building more accurate models of the deposition for use in
survey codes.
Institution: LOS ALAMOS NATL LAB, MS B229, LOS ALAMOS, NM 87544
Times Cited: 0
Bibliography: 15
Article:
http://linkseeker.lanl.gov/lanl?genre=article&issn=0748-1896&date=1996&volume=30&issue=3&spage=1311&atitle=Energetic+alpha+transport+in+a+magnetized+fusion+target&aulast=Kirkpatrick&auinit=RC
Title: US/Russian collaboration in high-energy-density physics using
high-explosive pulsed power: Ultrahigh current experiments, ultrahigh magnetic
field applications, and progress toward controlled thermonuclear fusion
Author: Lindemuth, IR; Ekdahl, CA; Fowler, CM; Reinovsky, RE; Younger, SM;
Chernyshev, VK; Mokhov, VN; Pavlovskii, AI
Journal: IEEE TRANSACTIONS ON PLASMA SCIENCE; DEC 1997; v.25, no.6, p.1357-1372
Doc. Type: Review
Abstract: A collaboration has been established between the All-Russian
Scientific Research Institute of Experimental Physics (VNIIEF) and the Los
Alamos National Laboratory (LANL), the two institutes which designed the first
nuclear weapons for their respective countries, In 1992, when emerging
governmental policy in the United States and Russia began to encourage
''lab-to-lab'' interactions, the two institutes quickly recognized a common
interest in the technology and applications of magnetic flux compression, the
technique for converting the chemical energy released by high-explosives into
intense electrical pulses and intensely concentrated magnetic energy, In a
period of just over three years, the two institutes have performed more than
fifteen joint experiments covering research areas ranging from basic pulsed
power technology to solid-state physics to controlled thermonuclear fusion,
Using magnetic flux compression generators, electrical currents ranging from 20
to 100 MA were delivered to loads of interest in high-energy-density physics, A
20-MA pulse was delivered to an imploding liner load with a 10-90% rise time of
0.7 mu s. A new, high-energy concept for soft X-ray generation was tested at 65
MA. More than 20 MJ of implosion kinetic energy was delivered to a condensed
matter imploding liner by a 100-MA current pulse. Magnetic flux compressors were
used to determine the upper critical field of a high-temperature superconductor
and to create pressure high enough that the transition from single particle
behavior to quasimolecular behavior was observed in solid argon, A major step
was taken toward the achievement of controlled thermonuclear fusion by a
relatively unexplored approach known in Russia as MAGO (MAGnitnoye Obzhatiye, or
''magnetic compression'') and in the United States as MTF (Magnetized Target
Fusion), Many of the characteristics of a target plasma that produced 10(13)
fusion neutrons have been evaluated, Computational models of the target plasma
suggest that the plasma is suitable for subsequent compression to fusion
conditions by an imploding pusher.
Institution: LOS ALAMOS NATL LAB, LOS ALAMOS, NM 87545; ALL RUSSIAN SCI RES INST
EXPT PHYS, SAROV, NIZHNI NOVGOROD, RUSSIA
Times Cited: 1
Bibliography: 38
Article:
http://linkseeker.lanl.gov/lanl?genre=article&issn=0093-3813&date=1997&volume=25&issue=6&spage=1357&atitle=US%2FRussian+collaboration+in+high%2Denergy%2Ddensity+physics+using+high%2Dexplosive+pulsed+power%3A+Ultrahigh+current+experiments%2C+ultrahigh+magnetic+field+applications%2C+and+progress+toward+controlled+thermonuclear+fusion&aulast=Lindemuth&auinit=IR
Title: Diagnostics for a magnetized target fusion experiment
Author: Wurden, GA; Intrator, TP; Clark, DA; Maqueda, RJ; Taccetti, JM; Wysocki,
FJ; Coffey, SK; Degnan, JH; Ruden, EL
Journal: REVIEW OF SCIENTIFIC INSTRUMENTS; JAN 2001; v.72, no.1, pt.2, p.552-555
Doc. Type: Article
Abstract: We are planning experiments using a field reversed configuration
plasma injected into a metal cylinder, which is subsequently electrically
imploded to achieve a fusing plasma. Diagnosing this plasma is quite challenging
due to the short timescales, high energy densities, high magnetic fields, and
difficult access. We outline our diagnostic sets in both a phase I study (where
the plasma will be formed and translated), and phase II study (where the plasma
will be imploded). The precompression plasma (diameter of only 8-10 cm, length
of 30-40 cm) is expected to have n similar to 10(17) cm(-3), T similar to
100-300 eV, B similar to 5 T, and a lifetime of 10-20 mus. We will use visible
laser interferometry across the plasma, along with a series of fiber-optically
coupled visible light monitors to determine the plasma density and position.
Excluded flux loops will be placed outside the quartz tube of the formation
region, but inside of the diameter of the theta -pinch formation coils. Impurity
emission in the visible and extreme ultraviolet range will be monitored
spectroscopically, and fast bolometers will measure the total radiated power. A
20 J Thomson scattering laser beam will be introduced in the axial direction,
and scattered light (from multiple spatial points) will be collected from the
sides. Neutron diagnostics (activation and time-resolved scintillation
detectors) will be fielded during both phases of the DD experiments. (C) 2001
American Institute of Physics.
Institution: Univ Calif Los Alamos Natl Lab, POB 1663, Los Alamos, NM 87545 USA;
Univ Calif Los Alamos Natl Lab, Los Alamos, NM 87545 USA; USAF, Res Lab,
Kirtland AFB, NM 87117 USA
Times Cited: 2
Bibliography: 9
Article:
http://linkseeker.lanl.gov/lanl?genre=article&issn=0034-6748&date=2001&volume=72&issue=1&spage=552&atitle=Diagnostics+for+a+magnetized+target+fusion+experiment&aulast=Wurden&auinit=GA
Title: Implosion of solid liner for compression of field reversed configuration
Author: Degnan, JH; Taccetti, JM; Cavazos, T; Clark, D; Coffey, SK; Faehl, RJ;
Frese, MH; Fulton, D; Gueits, JC; Gale, D; Hussey, TW; Intrator, TP; Kirpatrick,
RC; Kiuttu, GH; Lehr, FM; Letterio, JD; Lindemuth, I; McCullough, WF; Moses, R;
Peterkin, RE; Reinovsky, RE; Roderick, NF; Ruden, EL; Shlachter, JS; Schoenberg,
KF; Siemon, RE; Sommars, W; Turchi, PJ; Wurden, GA; Wysocki, F
Journal: IEEE TRANSACTIONS ON PLASMA SCIENCE; FEB 2001; v.29, no.1, p.93-98
Doc. Type: Article
Abstract: The design and first successful demonstration of an imploding solid
liner with height to diameter ratio, radial convergence, and uniformity suitable
for compressing a field reversed configuration is discussed. Radiographs
indicated a very symmetric implosion with no instability growth, with similar to
13 x radial compression of thp inner liner surface prior to impacting a central
measurement unit. The implosion kinetic energy was 1.5 megajoules, 34% of the
capacitor stored energy of 4.4 megajoules,
Institution: USAF, Res Lab, Directed Energy Directorate, Kirtland AFB, NM 87117
USA; USAF, Res Lab, Directed Energy Directorate, Kirtland AFB, NM 87117 USA;
Univ Calif Los Alamos Natl Lab, Los Alamos, NM 87545 USA; Maxwell Technol Inc,
Albuquerque, NM 87106 USA; NumerEx, Albuquerque, NM 87106 USA; Univ New Mexico,
Dept Chem & Nucl Engn, Albuquerque, NM 87131 USA
Times Cited: 4
Bibliography: 25
Article:
http://linkseeker.lanl.gov/lanl?genre=article&issn=0093-3813&date=2001&volume=29&issue=1&spage=93&atitle=Implosion+of+solid+liner+for+compression+of+field+reversed+configuration&aulast=Degnan&auinit=JH
Title: Isentropic focusing of supersonic plasma jets for magnetized target
fusion
Author: Winterberg, F
Journal: PHYSICS OF PLASMAS; AUG 2002; v.9, no.8, p.3540-3544
Doc. Type: Article
Abstract: It is shown that high energy flux densities can be reached by the
isentropic Prandtl-Meyer compression flow of a supersonic plasma jet in a
convergent nozzle. The energy flux density thereby increases in proportion to
M2/(gamma-1) where M is the Mach number of the jet and gamma the specific heat
ratio. With an axial magnetic field set up inside the nozzle by the
thermomagnetic Nernst effect, the jet is magnetically insulated from the nozzle
wall, reducing the bremsstrahlung radiation and conveniently magnetizing the
target plasma. A sufficiently large number of spherically arranged nozzles can
then be used for the ignition and confinement of a magnetized thermonuclear
target. (C) 2002 American Institute of Physics.
Institution: Univ Nevada, Reno, NV 89557 USA; Univ Nevada, Reno, NV 89557 USA
Times Cited: 0
Bibliography: 8
Article:
http://linkseeker.lanl.gov/lanl?genre=article&issn=1070-664x&date=2002&volume=9&issue=8&spage=3540&atitle=Isentropic+focusing+of+supersonic+plasma+jets+for+magnetized+target+fusion&aulast=Winterberg&auinit=F
Title: Heavy ion-plasma interaction of IFE concern: Where do we stand now?
Author: Deutsch, C; Nersysian, HB; Cereceda, C
Journal: LASER AND PARTICLE BEAMS; SEP 2002; v.20, no.3, p.463-466
Doc. Type: Article
Abstract: Two distinct issues of recent concern for ion-plasma interactions are
investigated. First, the subtle connection between quantum and classical ion
stopping is clarified by varying the space dimension. Then we evaluate the range
of thermonuclear a's in dense plasmas simultaneously magnetized and compressed.
Institution: Univ Paris 11, CNRS, UMR 8578, LPGP, F-91405 Orsay, France; Univ
Paris 11, CNRS, UMR 8578, LPGP, F-91405 Orsay, France; Univ Erlangen Nurnberg,
Inst Theoret Phys 2, D-91058 Erlangen, Germany; Univ Simon Bolivar, Dept Fis,
Caracas 1080A, Venezuela
Times Cited: 0
Bibliography: 6
Article:
http://linkseeker.lanl.gov/lanl?genre=article&issn=0263-0346&date=2002&volume=20&issue=3&spage=463&atitle=Heavy+ion%2Dplasma+interaction+of+IFE+concern%3A+Where+do+we+stand+now%3F&aulast=Deutsch&auinit=C
Title: Implosion and ignition of magnetized cylindrical targets driven by
heavy-ion beams
Author: Kemp, AJ; Basko, MM; Meyer-ter-Vehn, J
Journal: NUCLEAR FUSION; JAN 2003; v.43, no.1, p.16-24
Doc. Type: Article
Abstract: Implosions of cylindrical targets, directly driven by heavy-ion beams
irradiated along the cylinder axis, are investigated by one-dimensional
magneto-hydrodynamic simulations. In order to reduce heat losses from the hot
fuel, which is enclosed by a metallic tamper, an axial magnetic field is
introduced in the targets prior to implosions. We find that diffusive loss of
magnetic flux out of the fuel leads to an accumulation of fuel material next to
the cold pusher, causing a major problem for the efficiency of magnetized
implosions. Magnetized target fusion (MTF) is an important application of
magnetized cylindrical implosions. Looking for an optimum reference
configuration for MTF with heavy-ion beams, we find the ignition threshold of
magnetized cylindrical fusion targets to be at a driver pulse energy of about 10
MJ per centimetre target length; this value is nearly independent of target size
and driver power, while the fuel temperature is required to be larger than 50 eV
prior to implosions. Finally, we compare our reference case of an igniting MTF
target to a standard indirect-drive heavy-ion fusion target.
Institution: Gen Atom Co, San Diego, CA USA; Max Planck Inst Quantum Opt,
D-85748 Garching, Germany
Times Cited: 0
Bibliography: 13
Article:
http://linkseeker.lanl.gov/lanl?genre=article&issn=0029-5515&date=2003&volume=43&issue=1&spage=16&atitle=Implosion+and+ignition+of+magnetized+cylindrical+targets+driven+by+heavy%2Dion+beams&aulast=Kemp&auinit=AJ
Title: The MAGO system
Author: Garanin, SF
Journal: IEEE TRANSACTIONS ON PLASMA SCIENCE; AUG 1998; v.26, no.4, p.1230-1238
Doc. Type: Article
Abstract: Results of experimental and theoretical investigations are presented
in the frame of magnetohydrodynamic implosion conception MAGnitnoye Obzhatiye or
magnetic compression (MAGO). This approach suggests magnetized deuterium-tritium
(DT)-plasma preliminary heating and its subsequent adiabatic compression by
liner imploded by a magnetic field. DT-plasma preliminary heating is performed
using a special plasma chamber MAGO where magnetized plasma is accelerated in an
annular nozzle up to velocities similar to 100 cm/mu s and heated in arising
collisionless shock waves. Subsequent plasma compression and bringing of its
characteristics to the ignition can be realized using explosive magnetic
generators with energy 100-500 MJ. This paper discusses the plasma chamber MAGO,
physical effects essential for its operation, their relation with other plasma
physics areas, as well as problems arising in the MAGO system. Due to its
cylindrical symmetry with sole toroidal magnetic field component and essential
role of magnetohydrodynamics, the MAGO system and its problems are similar to
these in related systems, such as Z-pinches, plasma accelerators, and liner
systems.
Institution: ALL RUSSINA RES INST EXPT PHYS, SAROV 607190, RUSSIA
Times Cited: 1
Bibliography: 29
Article:
http://linkseeker.lanl.gov/lanl?genre=article&issn=0093-3813&date=1998&volume=26&issue=4&spage=1230&atitle=The+MAGO+system&aulast=Garanin&auinit=SF
Title: Kinetic theory of alpha particles production in a dense and strongly
magnetized plasma
Author: Cereceda, C; Deutsch, C; De Peretti, M; Sabatier, M; Basko, MM; Kemp, A;
Meyer-ter-Vehn, J
Journal: PHYSICS OF PLASMAS; NOV 2000; v.7, no.11, p.4515-4533
Doc. Type: Article
Abstract: In connection with fundamental issues relevant to magnetized target
fusion, the distribution function of thermonuclear alpha particles produced in
situ in a dense, hot, and strongly magnetized hydrogenic plasma considered fully
ionized in a cylindrical geometry is investigated. The latter is assumed in
local thermodynamic equilibrium with Maxwellian charged particles. The approach
is based on the Fokker-Planck equation with isotropic source S and loss s terms,
which may be taken arbitrarily under the proviso that they remain compatible
with a steady state. A novel and general expression is then proposed for the
isotropic and stationary distribution f(v). Its time-dependent extension is
worked out numerically. The solutions are valid for any particle velocity v and
plasma temperature T. Higher order magnetic and collisional corrections are also
obtained for electron gyroradius larger than Debye length. f(v) moments provide
particle diffusion coefficient and heat thermal conductivity. Their scaling on
collision time departs from Braginski's. (C) 2000 American Institute of Physics.
[S1070-664X(00)00211-1].
Institution: Univ Simon Bolivar, Dept Fis, Apdo 89000, Caracas 1080A, Venezuela;
UPS, LPGP, CNRS, F-91405 Orsay, France; CEN B3, F-91680 Bruyeres Le Chatel,
France; MPIQ, D-85748 Garching, Germany
Times Cited: 1
Bibliography: 28
Article:
http://linkseeker.lanl.gov/lanl?genre=article&issn=1070-664x&date=2000&volume=7&issue=11&spage=4515&atitle=Kinetic+theory+of+alpha+particles+production+in+a+dense+and+strongly+magnetized+plasma&aulast=Cereceda&auinit=C
Title: Dielectric response function and stopping power of dense magnetized
plasma
Author: Cereceda, C; Deutsch, C; Peretti, MD; Sabatier, M; Nersisyan, HB
Journal: PHYSICS OF PLASMAS; JUL 2000; v.7, no.7, p.2884-2893
Doc. Type: Article
Abstract: Using a kinetic-theoretic approach to Fokker-Planck equilibrium of
thermonuclear alpha particles in dense and magnetized plasmas, the corresponding
longitudinal dielectric function is investigated at length. It is used to
evaluate the energy loss of the alpha(s)(') through the excitation of collective
plasma modes. Specific attention was paid to the case of extreme magnetization,
as well as to the parallel stopping of alpha particles in dense and hot plasmas
of magnetized target fusion (MTF) interest. Maximum stopping is shown to be
strongly dependent on magnetic field intensity. (C) 2000 American Institute of
Physics. [S1070- 664X(00)00207-X].
Institution: Univ Simon Bolivar, Dept Fis, Apdo 89000, Caracas 1080A, Venezuela;
Univ Paris Sud, CNRS, UMR 8578, LPGP, F-91405 Orsay, France; CEN, F-91680
Bruyeres Le Chatel, France; Inst Radiophys & Elect, Div Theoret Phys, Ashtarak
378410, Armenia
Times Cited: 4
Bibliography: 19
Article:
http://linkseeker.lanl.gov/lanl?genre=article&issn=1070-664x&date=2000&volume=7&issue=7&spage=2884&atitle=Dielectric+response+function+and+stopping+power+of+dense+magnetized+plasma&aulast=Cereceda&auinit=C
Title: Ignition conditions for magnetized target fusion in cylindrical geometry
Author: Basko, MM; Kemp, AJ; Meyer-ter-Vehn, J
Journal: NUCLEAR FUSION; JAN 2000; v.40, no.1, p.59-68
Doc. Type: Article
Abstract: Ignition conditions in axially magnetized cylindrical targets are
investigated by examining the thermal balance of assembled DT fuel
configurations at stagnation. Special care is taken to adequately evaluate the
energy fraction of 3.5 MeV alpha particles deposited in magnetized DT cylinders.
A detailed analysis of the ignition boundaries in the rho R, T parametric plane
is presented. It is shown that the fuel magnetization allows a significant
reduction of the rho R ignition threshold only when the condition BR greater
than or similar to 6 x 10(5) G cm is fulfilled (B is the magnetic field strength
and R is the fuel radius).
Institution: CEA Cadarache, Dept Rech Fus Controlee, St Paul Durance, France;
CEA Cadarache, Dept Rech Fus Controlee, St Paul Durance, France; Max Planck Inst
Quantum Opt, D-8046 Garching, Germany
Times Cited: 5
Bibliography: 15
Article:
http://linkseeker.lanl.gov/lanl?genre=article&issn=0029-5515&date=2000&volume=40&issue=1&spage=59&atitle=Ignition+conditions+for+magnetized+target+fusion+in+cylindrical+geometry&aulast=Basko&auinit=MM
Copyright: ©2003 Inst. For Sci. Info
Article: | https://www.osti.gov/servlets/purl/765447-xUxfJw/webviewable/ | ||||
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Title: | MAGNETIZED TARGET FUSION FOR ADVANCED SPACE PROPULSION | ||||
Author: | Kirkpatrick, R.C. | ||||
Conference: | Space Technology and Applications International Forum, 18th Symposium on Space Nuclear Power and Propulsion (11 Feb 2001 - 14 Feb 2001: Albuquerque, NM (United States)) | ||||
Abstract: | No abstract prepared. | ||||
Doc.Type: | Conference publication; Report | ||||
Copyright: | (c) 2001 Contains copyrighted material | ||||
Holdings: | |||||
REPT | LA-UR-00-5010 c.1 STATUS: In Library | ||||
WWW | https://www.osti.gov/servlets/purl/765447-xUxfJw/webviewable/ Access restrictions may apply | ||||
Article: | http://lib-www.lanl.gov/cgi-bin/getfile?00538466.pdf | ||||
---|---|---|---|---|---|
Title: | MEASUREMENTS OF SOLID LINER IMPLOSION FOR MAGNETIZED TARGET FUSION | ||||
Author: | R. E. SIEMON; ET. AL. | ||||
Conference: | IAEA FUSION ENERGY CONFERENCE (4 Oct 2000 - 10 Oct 2000: SORRENTO (Italy)) | ||||
Abstract: | No abstract prepared. | ||||
Doc.Type: | Conference publication; Report | ||||
Copyright: | (c) 2001 Contains copyrighted material | ||||
Holdings: | |||||
REPT | LA-UR-00-4496 c.1 STATUS: In Library | ||||
WWW | http://lib-www.lanl.gov/cgi-bin/getfile?00538466.pdf 355KB Access restricted to selected government agencies | ||||
WWW | https://www.osti.gov/servlets/purl/763250-EbvVdD/webviewable/ Access restrictions may apply | ||||
Title: | Magnetized Target Fusion: a burning FRC plasma in an imploded metal can; New frontiers in plasma physics | |
---|---|---|
Author: | Wurden, G.A.; Milroy, R.D.; Wysocki, F.J.; Tuszewski, M.; Siemon, R.E.; Schoenberg, K.F.; Iguchi, H.; Ishiguro, S.; Tomita, Y.; Sato, T. | |
Conference: | ITC-9: 9. international Toki conference on plasma physics and controlled nuclear fusion (7 - 11 Dec 1998: Toki, Gifu (Japan)) | |
Abstract: | We are designing a compact (r=5 cm, l=30 cm), high density (n-10{sup 17}-10{sup 18} cm{sup -3}) Field Reversed Configuration (FRC) target plasma for Magnetized Target Fusion (MTF) experiments, using theta pinch formation techniques. The resulting FRC will then be translated into an aluminum linear for subsequent compression by implosion of the aluminium 'can'. The stored plasma energy will be modest ({approx}7.5 kJ), with average plasma beta of 1, and an initial external magnetic field strength of 5.4 T. Numerical modeling using the MOQUI FRC code shows that the required plasma can be formed using conical theta pinch coils, and our existing 0.25 MJ Colt capacitor bank, and then translated in a few microseconds into the aluminium linear, where it is trapped by mirror fields. We hope to demonstrate 10-fold cylindrical compression of the plasma with an imploding linear, which should allow significant burn in the resulting (deuterium) fusion-grade plasma. (author) | |
Doc.Type: | Article; Conference publication; Book part | |
Copyright: | (c) 2001 Contains copyrighted material |
Article: | http://lib-www.lanl.gov/cgi-bin/getfile?00796056.pdf | ||||
---|---|---|---|---|---|
Title: | ANALYSIS OF DATA FROM Z-PINCH MTF TARGET PLASMA EXPERIMENTS | ||||
Author: | F. WYSOCKI; ET AL; J. TACCETTI | ||||
Conference: | Conference title not supplied (Conference dates not supplied: Conference location not supplied) | ||||
Abstract: | The Los Alamos National Laboratory Colt facility has been used to create target plasma for Magnetized Target Fusion (MTF). The primary results regarding magnetic field, plasma density, plasma temperature, and hot plasma lifetime are summarized and the suitability of these plasma targets for MTF is assessed. | ||||
Doc.Type: | Conference publication; Report | ||||
Copyright: | (c) 2001 Contains copyrighted material | ||||
Holdings: | |||||
REPT | LA-UR-99-3581 c.1 STATUS: In Library | ||||
WWW | http://lib-www.lanl.gov/cgi-bin/getfile?00796056.pdf 241KB Access restricted to selected government agencies | ||||
Article: | https://www.osti.gov/servlets/purl/758788-w7PYj1/webviewable/ | ||||
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Title: | SIMPLE ONE-DIMENSIONAL TRANSPORT CODE FOR MAGNETIZED TARGET FUSION | ||||
Author: | STEFANO MIGLUIOLO - MIT | ||||
Report No.: | LA-SUB-00-6; DE00758788 (30 Oct 1999) | ||||
Abstract: | A one-dimensional (in space) time-dependent simulation code is development to study the transport of energy and particles in a field reversed configuration (FRC) plasma that is undergoing radial contraction. This contraction is due to an imploding metallic liner, which is treated through a boundary condition. | ||||
Doc.Type: | Report | ||||
Copyright: | (c) 2001 Contains copyrighted material | ||||
Holdings: | |||||
WWW | https://www.osti.gov/servlets/purl/758788-w7PYj1/webviewable/ Access restrictions may apply | ||||
Article: | http://linkseeker.lanl.gov/lanl?genre=article&issn=0730-9244&date=1999&spage=287&atitle=Solid%20liner%20inner%20surface%20phenomena%20during%20compression%20of%20a%20field%20reversed%20configuration%20plasma%20for%20a%20Magnetized%20Target%20Fusion%20proof%20of%20principle%20demonstration;%20The%2026th%20IEEE%20international%20conference%20on%20plasma%20science&aulast=Kiuttu&auinit=GF | ||||
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Title: | Solid liner inner surface phenomena during compression of a field reversed configuration plasma for a Magnetized Target Fusion proof of principle demonstration; The 26th IEEE international conference on plasma science | ||||
Author: | Kiuttu, G.F.; Faehl, R.J.; Turchi, P.J. | ||||
Conference: | 1999 IEEE International Conference on Plasma Science (20 Jun 1999 - 24 Jun 1999: Monterey, CA (United States)) | ||||
Abstract: | A proposed Magnetized Target Fusion (MTF) proof of principle demonstration involves compression of a field-reversed-configuration (FRC) plasma by a cylindrical, or quasi-spherical, solid liner. Peak internal poloidal magnetic fields are anticipated to be in the range of 1--10 MG at radial compression factors of approximately 10. Several phenomena occurring at the solid liner inner surface affect the performance of this plasma heating and compressions scheme. They include nonlinear magnetic field diffusion, phase changes and ablation due to surface and volumetric heating, and magnetohydrodynamic instability growth. Magnetic field diffusion limits the magnetic field amplification and reduces the magnetic flux buffer region between core plasma and liner. Melting and vaporization due to Joule heating alone have been shown to be likely to occur. Evaporated liner material traveling ahead of the liner solid surface can potentially interact deleteriously with the core plasma before peak compression. The authors present results of studies of the various phenomena using analytic models and 1- and 2-dimensional MHD simulations. | ||||
Doc.Type: | Article; Conference publication; Book part | ||||
Copyright: | (c) 2001 Contains copyrighted material | ||||
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Article: | http://linkseeker.lanl.gov/lanl?genre=article&issn=0730-9244&date=1999&spage=109&atitle=Computational%20investigation%20of%20plasma-wall%20interaction%20issues%20in%20magnetized%20target%20fusion;%20The%2026th%20IEEE%20international%20conference%20on%20plasma%20science&aulast=Sheehey&auinit=P | ||||
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Title: | Computational investigation of plasma-wall interaction issues in magnetized target fusion; The 26th IEEE international conference on plasma science | ||||
Author: | Sheehey, P.; Siemon, R.; Lindemuth, I.; Kirkpatrick, R.; Faehl, R.; Atchison, W. | ||||
Conference: | 1999 IEEE International Conference on Plasma Science (20 Jun 1999 - 24 Jun 1999: Monterey, CA (United States)) | ||||
Abstract: | In the concept known as Magnetized Target Fusion (MTF) in the US and Magnitnoye Obzhatiye (MAGO) in Russia, a preheated and magnetized target plasma is hydrodynamically compressed to fusion conditions. Because the magnetic field suppresses losses by electron thermal conduction in the fuel during the target implosion heating process, the implosion velocity may be much smaller than in traditional inertial confinement fusion. Hence liner-on-plasma compressions, magnetically driven using relatively inexpensive electrical pulsed power, may be practical. The relatively dense, hot target plasma, with starting conditions O(10{sup 18} cm{sup {minus}3}, 100 eV, 100 kG), may spend 10 or more microseconds in contact with a metal wall during formation and compression. Influx of a significant amount of high-Z wall material during this time could lead to excessive cooling by dilution and radiation that would prevent the desired near-adiabatic compression heating of the plasma to fusion conditions. Magnetohydrodynamic (MHD) calculations including detailed effects of radiation, heat conduction, and resistive field diffusion are being done, using several different computer codes, to investigate such plasma-wall interaction issues in ongoing MTF target plasma experiments and in proposed liner-on-plasma MTF experiments. | ||||
Doc.Type: | Article; Conference publication; Book part | ||||
Copyright: | (c) 2001 Contains copyrighted material | ||||
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Article: | http://www.osti.gov/servlets/purl/291164-Fqb1Jz/webviewable/ | ||||
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Title: | On the use of intense ion beams for generating magnetized target fusion plasma | ||||
Author: | Faehl, R.J.; Sheehey, P.; Lindemuth, I.R.; Wood, B.P. | ||||
Conference: | internatinal conference on high power particle beams (12.: 8-12 Jun 1998: Haifa (Israel)) | ||||
Abstract: | Magnetized Target Fusion (MTF) is a concept for creating a burning D-T plasma in a potentially inexpensive system. In essence, the concept involves ion heating on time scales short compared to ion transport times plus strong inhibition of thermal electron transport with a transverse magnetic field. The magnetic field is not intended to confine the ionic component. MTF is an intrinsically pulsed concept. A straightforward analysis of MTF indicates that D-T burning conditions can be achieved in compact plasma volumes with modest initial temperatures, through the use of pulsed power technology. In terms of size, density, temperature, and time scales, MTF occupies a position in phase space that is intermediate between steady MFE schemes and ICF. In terms of cost, it is one to two orders of magnitude less expensive than these. In this paper, the authors consider a possible method for creating the initial conditions adequate for the MTF concept through the use intense ion beam injection. | ||||
Doc.Type: | Conference publication; Report | ||||
Copyright: | (c) 2001 Contains copyrighted material | ||||
Holdings: | |||||
WWW | http://www.osti.gov/servlets/purl/291164-Fqb1Jz/webviewable/ 414KB Access restrictions may apply | ||||
Article: | http://www.osti.gov/servlets/purl/677121-Tc1SAM/webviewable/ | ||||
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Title: | Generation and compression of a target plasma for magnetized target fusion | ||||
Author: | Kirkpatrick, R.C.; Sheehey, P.T.; Lindemuth, I.R. | ||||
Report No.: | LA-UR-98-1861; DE99000557 ([1998]) | ||||
Abstract: | This is the final report of a three-year, Laboratory Directed Research and Development (LDRD) project at the Los Alamos National Laboratory (LANL). Magnetized target fusion (MTF) is intermediate between the two very different approaches to fusion: inertial and magnetic confinement fusion (ICF and MCF). Results from collaboration with a Russian MTF team on their MAGO experiments suggest they have a target plasma suitable for compression to provide an MTF proof of principle. This LDRD project had tow main objectives: first, to provide a computational basis for experimental investigation of an alternative MTF plasma, and second to explore the physics and computational needs for a continuing program. Secondary objectives included analytic and computational support for MTF experiments. The first objective was fulfilled. The second main objective has several facets to be described in the body of this report. Finally, the authors have developed tools for analyzing data collected on the MAGO and LDRD experiments, and have tested them on limited MAGO data. | ||||
Doc.Type: | Report | ||||
Copyright: | (c) 2001 Contains copyrighted material | ||||
Holdings: | |||||
WWW | http://www.osti.gov/servlets/purl/677121-Tc1SAM/webviewable/ 2.5MB Access restrictions may apply | ||||
Title: | Magnetic compression/magnetized target fusion (MAGO/MTF), an update | |
---|---|---|
Author: | Kirkpatrick, R.C.; Lindemuth, I.R. | |
Conference: | symposium on current trends in international fusion research: review and assessment (2.: 10-14 Mar 1997: Washington, DC (United States)) | |
Abstract: | Magnetized Target Fusion (MTF) was reported in two papers at the First Symposium on Current Trends in International Fusion Research. MTF is intermediate between two very different mainline approaches to fusion: Inertial Confinement Fusion (ICF) and magnetic confinement fusion (MCF). The only US MTF experiments in which a target plasma was compressed were the Sandia National Laboratory ``Phi targets''. Despite the very interesting results from that series of experiments, the research was not pursued, and other embodiments of MTF concept such as the Fast Liner were unable to attract the financial support needed for a firm proof of principle. A mapping of the parameter space for MTF showed the significant features of this approach. The All-Russian Scientific Research Institute of Experimental Physics (VNIIEF) has an on-going interest in this approach to thermonuclear fusion, and Los Alamos National Laboratory (LANL) and VNIIEF have done joint target plasma generation experiments relevant to MTF referred to as MAGO (transliteration of the Russian acronym for magnetic compression). The MAGO II experiment appears to have achieved on the order of 200 eV and over 100 KG, so that adiabatic compression with a relatively small convergence could bring the plasma to fusion temperatures. In addition, there are other experiments being pursued for target plasma generation and proof of principle. This paper summarizes the previous reports on MTF and MAGO and presents the progress that has been made over the past three years in creating a target plasma that is suitable for compression to provide a scientific proof of principle experiment for MAGO/MTF. | |
Doc.Type: | Conference publication; Report | |
Copyright: | (c) 2001 Contains copyrighted material |
Article: | http://lib-www.lanl.gov/cgi-bin/getfile?00393978.pdf | ||||
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Title: | Magnetized Target Fusion. A Proof-of-Principle Research Proposal | ||||
Author: | Schoenberg, K.F.; Siemon, R.E. | ||||
Report No.: | LA-UR-98-2413; DE00763201 (19 May 1998) | ||||
Abstract: | No abstract prepared. | ||||
Doc.Type: | Report | ||||
Copyright: | (c) 2001 Contains copyrighted material | ||||
Holdings: | |||||
WWW | http://lib-www.lanl.gov/cgi-bin/getfile?00393978.pdf 784KB Access restricted to selected government agencies | ||||
WWW | https://www.osti.gov/servlets/purl/763201-C39eCy/webviewable/ Access restrictions may apply | ||||
Title: | Controlled thermonuclear fusion:faster, quicker, cheaper approaches using magnetized target fusion; 6. Ukrainian conference and school on plasma physics and controlled fusion as a section of conference 'Physics in Ukraine' | |
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Author: | Schoenberg, K.F.; Moses, R.W.; Gerwin, R.A.; Siemon, R. | |
Conference: | Ukrainian conference and school on plasma physics and controlled fusion as a section of conference 'Physics in Ukraine' (6.: 14 - 20 Sep 1998: Alushta (Ukraine)) | |
Abstract: | No abstract prepared | |
Doc.Type: | Article; Conference publication; Miscellaneous part | |
Copyright: | (c) 2001 Contains copyrighted material |
Article: | https://www.osti.gov/servlets/purl/760030-KXdwaA/webviewable/ | ||||
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Title: | Magnetized Target Fusion (MTF): Principles, Status, and International Collaboration | ||||
Author: | Kirkpatrick, R.C. | ||||
Conference: | Latin American Workshop on Plasma Physics (16 Nov 1998 - 27 Nov 1998: Tandil (Argentina)) | ||||
Abstract: | Magnetized target fusion (MTF) is an approach to thermonuclear fusion that is intermediate between the two extremes of inertial and magnetic confinement. Target plasma preparation is followed by compression to fusion conditions. The use of a magnetic field to reduce electron thermal conduction and potentially enhance DT alpha energy deposition allows the compression rate to be drastically reduced relative to that for inertial confinement fusion. This leads to compact systems with target driver power and intensity requirements that are orders of magnitude lower than for ICF. A liner on plasma experiment has been proposed to provide a firm proof of principle for MTF. | ||||
Doc.Type: | Conference publication; Report | ||||
Copyright: | (c) 2001 Contains copyrighted material | ||||
Holdings: | |||||
WWW | https://www.osti.gov/servlets/purl/760030-KXdwaA/webviewable/ Access restrictions may apply | ||||
Title: | Modeling of Present and Proposed Magnetized Target Fusion Experiments | |
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Author: | Sheehey, P.T.; Lindemuth, I.R.; Kirkpatrick, R.C.; Faehl, R.J. | |
Conference: | Megagauss-VIII, Eight International conference on MegaGauss Magnetic Field Generation and Related Topics (18 Oct 1998 - 23 Oct 1998: Tallahassee, FL (United States)) | |
Abstract: | In the concept known as Magnetized Target Fusion (MTF) in the United States and Magnitnoye Obzhatiye (MAGO) in Russia, a preheated and magnetized target plasma is hydrodynamically compressed to fusion conditions. Because the magnetic field suppresses losses by electron thermal conduction in the fuel during the target implosion heating process, the compression may be over a much longer time scale than in traditional inertial confinement fusion. Hence ''liner-on-plasma'' compressions, magnetically driven using relatively inexpensive electrical pulsed power, may be practical. One candidate target plasma known as ''MAGO'' was originated in Russia and is now being jointly developed by the All-Russian Scientific Research Institute of Experimental Physics (VNIIEF) and Los Alamos National Laboratory (LANL). Other possible target plasmas now under investigation at LANL include wall-supported deuterium-fiber-initiated Z-pinches and compact toroids. Detailed computational modeling is being done of such target plasmas. In addition, liner-on-plasma compressions of such target plasmas to fusion conditions are being computationally modeled, and experimental and computational investigation of liner implosions suitable for MTF is continuing. Results will be presented. | |
Doc.Type: | Conference publication; Report | |
Copyright: | (c) 2001 Contains copyrighted material |
Article: | http://infoserve.sandia.gov/sand_doc/1998/981591.pdf | ||||
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Title: | Computational modeling of joint U.S.-Russian experiments relevant to magnetic compression/magnetized target fusion (MAGO/MTF); Proceedings of the 5. joint Russian-American computational mathematics conference | ||||
Author: | Sheehey, P.T.; Lindemuth, I.R.; Kirkpatrick, R.C.; Faehl, R.J. | ||||
Conference: | joint Russian-American computational mathematics conference (5.: 2-5 Sep 1997: Albuquerque, NM (United States)) | ||||
Abstract: | Magnetized Target Fusion (MTF) experiments, in which a preheated and magnetized target plasma is hydrodynamically compressed to fusion conditions, present some challenging computational modeling problems. Recently, joint experiments relevant to MTF (Russian acronym MAGO, for Magnitnoye Obzhatiye, or magnetic compression) have been performed by Los Alamos National Laboratory and the All-Russian Scientific Research Institute of Experimental Physics (VNIIEF). Modeling of target plasmas must accurately predict plasma densities, temperatures, fields, and lifetime; dense plasma interactions with wall materials must be characterized. Modeling of magnetically driven imploding solid liners, for compression of target plasmas, must address issues such as Rayleigh-Taylor instability growth in the presence of material strength, and glide plane-liner interactions. Proposed experiments involving liner-on-plasma compressions to fusion conditions will require integrated target plasma and liner calculations. Detailed comparison of the modeling results with experiment will be presented. | ||||
Doc.Type: | Article; Conference publication; Report part | ||||
Copyright: | (c) 2001 Contains copyrighted material | ||||
Holdings: | |||||
WWW | http://infoserve.sandia.gov/sand_doc/1998/981591.pdf Access restrictions may apply | ||||
Title: | Progress with developing a target for magnetized target fusion; IEEE conference record -- Abstracts | |
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Author: | Wysocki, F.J.; Sheehey, P.T.; Lindemuth, I.R.; Kirkpatrick, R.C.; Whiteson, D.O.; Oona, H.; Idzorek, G.; Chrien, B.E. | |
Conference: | IEEE international conference on plasma science (24.: 19-23 May 1997: San Diego, CA (United States)) | |
Abstract: | Magnetized Target Fusion (MTF) is an approach to fusion where a preheated and magnetized plasma is adiabatically compressed to fusion conditions. Successful MTF requires a suitable initial target plasma with an embedded magnetic field of at least 5 T in a closed-field-line topology, a density of roughly 10{sup 18} cm{sup {minus}3}, a temperature of at least 50 eV, and must be free of impurities which would raise radiation losses. Target plasma generation experiments are underway at Los Alamos National Laboratory using the Colt facility; a 0.25 MJ, 2--3 {micro}s rise-time capacitor bank. In the first experiments, a Z-pinch is produced in a 2 cm radius by 2 cm high conducting wall using a static gas-fill of hydrogen or deuterium gas in the range of 0.5 to 2 torr. Follow-on experiments will use a frozen deuterium fiber along the axis (without a gas-fill). The diagnostics include B-dot probes, framing camera, gated OMA visible spectrometer, time-resolved monochrometer, silicon photodiodes, neutron yield, and plasma-density interferometer. Operation to date has been with drive current ranging from 0.8 MA to 1.9 MA. Optical diagnostics show that the plasma produced in the containment region lasts roughly 20 to 30 {micro}s, and the B-dot probes show a broad current-profile in the containment region. The experimental design and data will be presented. | |
Doc.Type: | Article; Conference publication; Book part | |
Copyright: | (c) 2001 Contains copyrighted material |
1. Science Server at LANL
Computational and experimental investigation of magnetized target fusion
Sheehey, P.; Guzik, J.; Kirkpatrick, R.; Lindemuth, I.; Scudder, D.; Wysocki, F.
Los Alamos Nat. Lab., NM, USA
IEEE International Conference on Plasma Science; Boston, MA, USA; June 3, 1996
pp. 110
Summary form only given, as follows. In magnetized target fusion (MTF), a
preheated and magnetized target plasma is hydrodynamically compressed to fusion
conditions. Because the magnetic field suppresses losses by electron thermal
conduction in the fuel during the target implosion heating process, the
compression may be over a much longer time scale than in traditional inertial
confinement fusion. Bigger targets and much lower initial target densities than
in ICF can be used, reducing radiative energy losses. Therefore,
"liner-on-plasma" compressions, driven by relatively inexpensive electrical
pulsed power, may be practical. Potential MTF target plasmas must meet minimum
temperature, density, and magnetic field starting conditions, and must remain
relatively free of high-Z radiation-cooling-enhancing contaminants. At Los
Alamos National Laboratory, computational and experimental research is being
pursued into MTF target plasmas, such as deuterium-fiber-initiated Z-pinches,
and the Russian-originated "MAGO" plasma. In addition, liner-on-plasma
compressions of such target plasmas to fusion conditions are being
computationally modeled, and experimental investigation of such heavy liner
implosions has begun.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee1912&issue=v1996i0306&article=110_caeiomtf
PLASMA
2. Science Server at LANL
Computational modeling of pulsed-power-driven magnetized target fusion
experiments
Sheehey, P.; Kirkpatrick, R.; Lindemuth, I.
Los Alamos Nat. Lab., NM, USA
IEEE Internation Pulsed Power Conference; Albuquerque, NM, USA; July 3, 1995
pp. 1030 - 1035
Direct magnetic drive using electrical pulsed power has been considered
impractically slow for traditional inertial confinement implosion of fusion
targets. However, if the target contains a preheated, magnetized plasma,
magnetothermal insulation may allow the near-adiabatic compression of such a
target to fusion conditions on a much slower time scale. 100 MJ-class explosive
flux compression generators, with implosion kinetic energies far beyond those
available with conventional fusion drivers, are an inexpensive means to
investigate such magnetized target fusion (MTF) systems. One means of obtaining
the preheated and magnetized plasma required for an MTF system is the recently
reported "MAGO" concept. MAGO is a unique, explosive-pulsed-power driven
discharge in two cylindrical chambers joined by an annular nozzle. Joint
Russian-American MAGO experiments have reported D-T neutron yields in excess of
1013 from this plasma preparation stage alone, without going on to
the proposed separately driven MTF implosion of the main plasma chamber. 2-D MHD
computational modeling of MAGO discharges shows good agreement with experiments.
The calculations suggest that after the observed neutron pulse, a diffuse
Z-pinch plasma with temperature in excess of 100 eV is created, which may be
suitable for subsequent MTF implosion, in a heavy liner magnetically driven by
explosive pulsed power. Other MTF concepts, such as fiber-initiated Z-pinch
target plasmas, are also being computationally and theoretically evaluated. The
status of the authors' modeling efforts are reported.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee2015&issue=v1995i0307_2&article=1030_cmopmtfe
PPC
3. Science Server at LANL
Target development for magnetized target fusion at LANL
Wysocki, F.J.; Sheehey, P.T.
Los Alamos Nat. Lab., NM, USA
IEEE International Conference on Plasma Science; Boston, MA, USA; June 3, 1996
pp. 250
Summary form only given. Magnetized Target Fusion (MTF) is an approach to fusion
where a preheated and magnetized plasma is adiabatically compressed to fusion
conditions. Compared to traditional inertial confinement fusion (ICF), the
magnetic field substantially reduces electron thermal conduction losses, and
lower initial density (of order 1018 cm-3) reduces
radiation losses. This allows the larger targets (cm scale) to be imploded at
much reduced speed (1 cm/μS).
Successful MTF requires a suitable initial target plasma with a magnetic field
of at least 5 T in a closed-field-line topology, a density of roughly 1018
cm-3, a temperature of at least 50 eV, and must be free of impurities
which would raise radiation losses. The required compression ratio needed to
reach fusion conditions is directly dependent on the initial plasma temperature,
and thus, an initial temperature of 100-300 eV would be desirable. Target plasma
generation experiments are beginning at Los Alamos National Laboratory using the
Colt facility; a 0.25 MJ, 3 μs
rise-time capacitor bank. The goal of these experiments is to demonstrate plasma
conditions meeting the minimum requirements for a MTF initial target plasma. The
first experiments will examine Z-pinches produced in a 2 cm radius by 2 cm high
conducting wall, using either a gas-fill (with possible laser-initiated channel
along the geometric axis), or a frozen deuterium fiber along the axis. The
experimental design and any preliminary data will be presented.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee1912&issue=v1996i0306&article=250_tdfmtfal
PLASMA
4. Science Server at LANL
MHD modeling of magnetized target fusion experiments
Sheehey, P.T.; Faehl, R.J.; Kirkpatrick, R.C.; Lindemuth, I.R.
Los Alamos Nat. Lab., NM, USA
Pulsed Power Plasma Science; Las Vegas, NV, USA; June 17, 2001
pp. 491
Summary form only given. Magnetized Target Fusion (MTF) is an alternate approach
to controlled fusion in which a dense
10 e 17-18 cm-3, preheated
200 eV, and magnetized
100 kG target plasma is
hydrodynamically compressed by an imploding liner. If electron thermal
conduction losses are magnetically suppressed, relatively slow
1 cm/microsecond "liner-on-plasma"
compressions may be practical, using liners driven by inexpensive pulsed power.
Target plasmas need to remain relatively free of potentially cooling
contaminants during formation and compression. Magnetohydrodynamic (MHD)
calculations including detailed effects of radiation, heat conduction, and
resistive field diffusion have been used to model separate static target plasma
(Russian MAGO, Field Reversed Configuration at Los Alamos National Laboratory)
and liner implosion experiments (without plasma fill), such as recently
performed at the Air Force Research Laboratory (Albuquerque). Using several
different codes, proposed experiments in which such liners are used to compress
such target plasmas are now being modeled in one and two dimensions. In this
way, it is possible to begin to investigate important issues for the design of
such proposed liner-on-plasma fusion experiments. The competing processes of
implosion, heating, mixing, and cooling will determine the potential for such
MTF experiments to achieve fusion conditions.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee2837&issue=v2001i1706&article=491_mmomtfe
PPPOS
5. Science Server at LANL
MHD modeling of magnetized target fusion experiments
Sheehey, P.T.; Faehl, R.J.; Kirkpatrick, R.C.; Lindemuth, I.R.
Los Alamos Nat. Lab., NM, USA
Pulsed Power Plasma Science; Las Vegas, NV, USA; June 17, 2001
pp. 1603 - 1606
Magnetized Target Fusion (MTF) is an alternate approach to controlled fusion in
which a dense (O(1017-18 cm-3)), preheated (O(200 eV)),
and magnetized (O(100 kG)) target plasma is hydrodynamically compressed by an
imploding liner. If electron thermal conduction losses are magnetically
suppressed, relatively slow O(1 cm/microsecond) "liner-on-plasma" compressions
may be practical, using liners driven by inexpensive electrical pulsed power.
Target plasmas need to remain relatively free of potentially cooling
contaminants during formation and compression. Magnetohydrodynamic (MHD)
calculations including detailed effects of radiation, heat conduction, and
resistive field diffusion have been used to model separate target plasma
(Russian MAGO, Field Reversed Configuration at Los Alamos National Laboratory)
and liner implosion experiments (without plasma fill), such as recently
performed at the Air Force Research Laboratory (Albuquerque). Using several
different codes, proposed experiments in which such liners are used to compress
such target plasmas are now being modeled in one and two dimensions. In this
way, it is possible to begin to investigate important issues for the design of
such proposed liner-on-plasma fusion experiments. The competing processes of
implosion, heating, mixing, and cooling will determine the potential for such
MTF experiments to achieve fusion conditions.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee2837&issue=v2001i1706_2&article=1603_mmomtfe
PPPS
6. Science Server at LANL
Computational modeling of pulsed-power-driven magnetized target fusion
experiments
Sheehey, P.; Kirkpatrick, R.; Lindemuth, I.
Los Alamos Nat. Lab., NM, USA
IEEE International Conference on Plasma Science; Madison, WI, USA; June 5, 1995
pp. 253 - 254
Summary form only given, as follows. Direct magnetic drive using electrical
pulsed power has been considered impractically slow for traditional inertial
confinement implosion of fusion targets. However, if the target contains a
preheated, magnetized plasma, magnetothermal insulation may allow the
near-adiabatic compression of such a target to fusion conditions on a much
slower time scale. 100-MJ-class explosive flux compression generators, with
implosion kinetic energies far beyond those available with conventional fusion
drivers, are an inexpensive means to investigate such magnetized target fusion (MTF)
systems. One means of obtaining the preheated and magnetized plasma required for
an MTF system is the recently reported "MAGO" concept. MAGO is a unique,
explosive-pulsed-power-driven discharge in two cylindrical chambers joined by an
annular nozzle. Joint Russian-American MAGO experiments have reported D-T
neutron yields in excess of 1013 from this plasma preparation stage
alone, without going on to the proposed separately driven MTF implosion of the
main plasma chamber. Two-dimensional MHD computational modeling of MAGO
discharges shows good agreement to experiment. The calculations suggest that
after the observed neutron pulse, a diffuse Z-pinch plasma with temperature in
excess of 100 eV is created, which may be suitable for subsequent MTF implosion,
in a heavy liner magnetically driven by explosive pulsed power. Other MTF
concepts, such as fiber-initiated Z-pinch target plasmas, are also being
computationally and theoretically evaluated. The status of our modeling efforts
are reported.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee1912&issue=v1995i0506&article=253_cmopmtfe
PLASMA
7. Science Server at LANL
Computational investigation of plasma-wall interaction issues in magnetized
target fusion
Sheehey, P.; Atchison, W.; Faehl, R.; Kirkpatrick, R.; Lindemuth, I.; Siemon, R.
Los Alamos Nat. Lab., NM, USA
IEEE Internation Pulsed Power Conference; Monterey, CA, USA; June 27, 1999
pp. 888 - 891
In the concept known as magnetized target fusion (MTF) in the United States and
magnitnoye obzhatiye (MAGO) in Russia, a preheated and magnetized target plasma
is hydrodynamically compressed to fusion conditions. Because the magnetic field
suppresses losses by electron thermal conduction in the fuel during the target
implosion heating process, the implosion velocity may be much smaller than in
traditional inertial fusion. Hence "liner-on-plasma" magnetically driven using
relatively inexpensive electrical pulsed power, may be practical. The relatively
dense, hot target plasma, with starting conditions O(1018 cm-3,
100 eV, 100 kG), may spend 10 or more microseconds in contact with a metal wall
during formation and compression. Influx of a significant amount of high-Z wall
material during this time could lead to excessive cooling by dilution and
radiation that would prevent the desired near-adiabatic compression heating of
the plasma to fusion conditions. Magnetohydrodynamic (MHD) calculations
including detailed effects of radiation, heat conduction, and resistive field
diffusion are being done, using several different computer codes, to investigate
such plasma-wall interaction issues in ongoing MTF target plasma experiments and
in proposed liner-on-plasma MTF experiments.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee2015&issue=v1999i2706_2&article=888_ciopiiimtf
PPC
8. Science Server at LANL
Computational investigation of plasma-wall interaction issues in magnetized
target fusion
Sheehey, P.; Atchison, W.; Faehl, R.; Kirkpatrick, R.; Lindemuth, I.; Siemon, R.
Los Alamos Nat. Lab., NM, USA
IEEE International Conference on Plasma Science; Monterey, CA, USA; June 20,
1999
pp. 109
Summary form only given. In the concept known as Magnetized Target Fusion (MTF)
in the United States and Magnitnoye Obzhatiye (MAGO) in Russia, a preheated and
magnetized target plasma is hydrodynamically compressed to fusion conditions.
Because the magnetic field suppresses losses by electron thermal conduction in
the fuel during the target implosion heating process, the implosion velocity may
be much smaller than in traditional inertial confinement fusion. Hence
"liner-on-plasma" compressions, magnetically driven using relatively inexpensive
electrical pulsed power, may be practical. The relatively dense, hot target
plasma, with starting conditions O(1018 cm-3, 100 eV, 100
kG), may spend 10 or more microseconds in contact with a metal wall during
formation and compression. Influx of a significant amount of high-Z wall
material during this time could lead to excessive cooling by dilution and
radiation that would prevent the desired near-adiabatic compression heating of
the plasma to fusion conditions. Magnetohydrodynamic (MHD) calculations
including detailed effects of radiation, heat conduction, and resistive field
diffusion are being done, using several different computer codes, to investigate
such plasma-wall interaction issues in ongoing MTF target plasma experiments and
in proposed liner-on-plasma MTF experiments.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee1912&issue=v1999i2006&article=109_ciopiiimtf
PLASMA
9. Science Server at LANL
Implosion and ignition of magnetized cylindrical targets driven by heavy-ion
beams
Meyer-ter-Vehn, J.
Max-Planck-Institut für Quantenoptik, Hans-Kopfermann-Str. 1, 85748 Garching,
Germany
Nuclear Fusion ; January 01, 2003; vol.43, no.1, pp. 16-24
Implosions of cylindrical targets, directly driven by heavy-ion beams irradiated
along the cylinder axis, are investigated by one-dimensional
magneto-hydrodynamic simulations. In order to reduce heat losses from the hot
fuel, which is enclosed by a metallic tamper, an axial magnetic field is
introduced in the targets prior to implosions. We find that diffusive loss of
magnetic flux out of the fuel leads to an accumulation of fuel material next to
the cold pusher, causing a major problem for the efficiency of magnetized
implosions. Magnetized target fusion (MTF) is an important application of
magnetized cylindrical implosions. Looking for an optimum reference
configuration for MTF with heavy-ion beams, we find the ignition threshold of
magnetized cylindrical fusion targets to be at a driver pulse energy of about
10 MJ per centimetre target length; this value is nearly independent of target
size and driver power, while the fuel temperature is required to be larger than
50 eV prior to implosions. Finally, we compare our reference case of an igniting
MTF target to a standard indirect-drive heavy-ion fusion target.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=journals&journal=00295515&issue=v43i0001&article=16_iaiomctdbhb
10. Science Server at LANL
The inverse Z-pinch as a physics test bed, and, possibly, a target plasma, for
magnetized target fusion
Lindemuth, I.; Kirkpatrick, R.; Sheehey, P.; Siemon, R.; Bauer, B.; Makhin, V.;
Presura, R.; Fuelling, S.
Los Alamos Nat. Lab., NM, USA
IEEE International Conference on Plasma Science; Banff, Alta., Canada; May 26,
2002
pp. 235
Summary form only given, as follows. From an overall fusion system perspective,
the possibility of compressing a magnetized target plasma with beta greater than
unity by a magnetically driven imploding liner, or other target pusher driver,
appears very exciting. This approach, known as magnetized target fusion (MTF),
operates in a density regime that is intermediate between the twelve orders of
magnitude in density that separate MFE and ICF. Even if plasma transport is Bohm-like,
the MTF parameter space appears accessible with existing drivers, i.e., MTF does
not require a major financial investment in driver technology. The confinement
directly by material walls and the thermal transport of magnetized, high-beta
plasma in the MTF regime has been studied only a little, theoretically,
computationally, and experimentally. We are computationally evaluating, using
the well-benchmarked two-dimensional radiation-MHD code MHRDR, and other tools
as appropriate, the inverse z-pinch as an experimental test bed to study MTF
transport and confinement. Existing facilities being considered include the
2terawatt Zebra generator at the Nevada Terawatt Facility, the Colt capacitor
bank at LANL, and the Atlas capacitor bank at LANL. According to MHRDR, the
plasma is expected to evolve into a near-equilibrium. Thin sheaths next to the
outer cylinder and end walls contain steep temperature and density gradients.
The plasma should take microseconds to cool, even in the presence of
considerable convection. This cooling rate is much slower than would result if
free-streaming losses of ions or unmagnetized-electron conduction losses were
present. Experimental verification and understanding of the energy transport in
this simple wall-confined plasma would provide increased confidence in the
design of integrated liner-on-plasma experiments. We are also evaluating the
inverse z-pinch as an MTF target plasma for integrated liner-on-plasma
experiments.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee1912&issue=v2002i2605&article=235_tizaaptpfmtf
PLASMA
11. Science Server at LANL
A Physics Exploratory Experiment on Plasma Liner Formation
Thio, Y. C. Francis; Knapp, Charles E.; Kirkpatrick, Ronald C.; Siemon, Richard
E.; Turchi, Peter J.
Journal of Fusion Energy ; June 2001; vol.20, no.1, pp. 1-11
Momentum flux for imploding a target plasma in magnetized target fusion (MTF)
may be delivered by an array of plasma guns launching plasma jets that would
merge to form an imploding plasma shell (liner). In this paper, we examine what
would be a worthwhile experiment to explore the dynamics of merging plasma jets
to form a plasma liner as a first step in establishing an experimental database
for plasma-jets-driven magnetized target fusion (PJETS-MTF). Using past
experience in fusion energy research as a model, we envisage a four-phase
program to advance the art of PJETS-MTF to fusion breakeven (Q
1). The experiment (PLX) described
in this paper serves as Phase 1 of this four-phase program. The logic underlying
the selection of the experimental parameters is presented. The experiment
consists of using 12 plasma guns arranged in a circle, launching plasma jets
toward the center of a vacuum chamber. The velocity of the plasma jets chosen is
200 km/s, and each jet is to carry a mass of 0.2 mg to 0.4 mg. A candidate
plasma accelerator for launching these jets consists of a coaxial plasma gun of
the Marshall type.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=journals&journal=01640313&issue=v20i0001&article=1_apeeoplf
12. Science Server at LANL
An embodiment of the magnetized target fusion concept in a spherical geometry
with stand-off drivers
Thio, Y.C.F.; Kirkpatrick, R.C.; Knapp, C.; Panarella, E.; Wysocki, F.J.; Parks,
P.
Los Alamos Nat. Lab., NM, USA
IEEE International Conference on Plasma Science; Raleigh, NC, USA; June 1, 1998
pp. 266
Summary form only given. An innovative fusion scheme, embodying the principles
of magnetized target fusion (MTF), in which the initial magnetized target and a
plasma liner containing a cold fuel layer are introduced into the reactor vessel
in a stand-off manner, is discussed. Two compact toroids containing fusionable
materials are introduced into a spherical reactor target chamber in a
diametrically opposing manner. Embedded in the compact toroids are force-free
magnetic fields in Woltjer-Wells-Taylor's state of minimum energy, which are
known experimentally to be extraordinarily stable. They collide in the center to
form an initial magnetized target plasma. A spherical distribution of plasma
jets are then launched from the periphery of the vessel, coalescing to form a
converging spherical plasma liner. On impact with the central plasma, the plasma
liner sends a shock wave through it, shock heating it to some elevated
temperature (above 100 eV) which sets the initial adiabat for subsequent
compression. The high temperature immediately raises the electrical conductivity
of the plasma to the extent that it traps the magnetic flux inside the central
plasma, The central plasma is further compressed by the plasma liner and heated
nearly adiabatically to conditions for thermonuclear burn, the magnetic flux
being compressed with it. The thermal loss rate, greatly reduced by the high
magnetic fields, are sufficiently low that the compression heating can be
achieved relatively slowly using plasma jets with velocity of the order of 10-50
cm per microsecond, velocities which have been achieved in the laboratory using
electromagnetic acceleration.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee1912&issue=v1998i0106&article=266_aeotmtasgwsd
PLASMA
13. Science Server at LANL
Proposed generation and compression of a target plasma for MTF
Kirkpatrick, R.C.; Thurston, R.S.; Chrein, R.E.; Guzik, J.A.; Sgro, A.G.;
Scudder, D.W.; Wysocki, F.J.; Fernandez, J.C.; Shlachter, J.S.; Lindemuth, I.R.;
Sheehey, P.T.
Los Alamos Nat. Lab., NM, USA
IEEE Internation Pulsed Power Conference; Albuquerque, NM, USA; July 3, 1995
pp. 1047 - 1051
Magnetized target fusion (MTF), in which a magnetothermally insulated plasma is
hydrodynamically compressed to fusion conditions, represents an approach to
controlled fusion which avoids difficulties of both traditional inertial
confinement and magnetic confinement approaches. It appears possible to compress
a magnetothermally insulated plasma to fusion ignition conditions using
existing, relatively inexpensive drivers, such as pulsed power devices
(including explosive pulsed power). Hence, MTF may represent a means to
demonstrate and study ignited plasmas with a very small capital investment. An
ongoing LANL explosive pulsed power collaboration with the Russian VNIIEF
Laboratory at Arzamas 16 is partly motivated by this application. We are
proposing to demonstrate the feasibility of magnetized target fusion by: (1)
creating a suitable magnetized target plasma, and (2) performing preliminary
liner compression experiments using existing pulsed power facilities and
demonstrated liner performance. The required plasma conditions vary for
different drivers, but are approximately described by temperature >50 eV,
density >10-6 gm/cm3, current of several hundred
kiloamperes, and dimensions of one to a few cm (giving an embedded magnetic
field of about 50 kG). The initial candidate for creating the target plasma is a
fiber-initiated Z-pinch. These pinches have already been created with relevant
parameters, but need to be optimized for the MTF application. The target plasma
would be diagnosed and optimized inside a static liner, using interferometry,
spectroscopy, and other diagnostic tools.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee2015&issue=v1995i0307_2&article=1047_pgacoatpfm
PPC
14. Science Server at LANL
Numerical simulations of Plasma/Magnetic Field/Liner interactions in magnetized
target fusion systems
Roderick, N.F.; Douglas, M.R.; Peterkin, R.E., Jr.; Turchi, P.J.; Degnan, J.H.;
Frese, M.H.
Directed Energy Directorate, Air Force Res. Lab., USA
Pulsed Power Plasma Science; Las Vegas, NV, USA; June 17, 2001
pp. 537
Summary form only given. Magnetized target fusion (MTF) relies on magnetic field
suppression of thermal transport to achieve fusion conditions at relatively low
driver power. One method proposed for MTF uses an imploding liner which starts
at solid density to compress a hot magnetized plasma. Analytic methods and one
and two dimensional magnetohydrodynamic simulations are being used to study this
plasma liner compression approach. Plasma from the liner walls represents a
contaminant that can increase radiation losses and lower plasma temperatures
below desired values. As part of this effort are we are investigating the
generation and evolution of such plasmas. Energy input to the liner from thermal
conduction and joule heating from both the magnetized plasma and the driving
magnetic field are under study to determine their contributions to the
production of contaminant and the interaction of these plasmas with the hot
fusion plasma. Results from these ongoing calculations will be presented.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee2837&issue=v2001i1706&article=537_nsopfiimtfs
PPPOS
15. Science Server at LANL
Magnetized target fusion ignition conditions
de Peretti, R.; Sabatier, M.
CEA, Centre d'Etudes de Limeil-Valenton, Villeneuve St. Geor, France
IEEE International Conference on Plasma Science; Madison, WI, USA; June 5, 1995
pp. 194
Magnetized Target Fusion (MTF) consists of the hydrodynamic compression of a
wall, hot, magnetized DT plasma to ignition conditions. MTF takes advantage of
two benefits of a magnetic field in a plasma: reduction of the thermal
conductivity and enhancement of the charged particle reaction product energy
deposition. To study the ignition conditions, we evaluate the gains brought by
compression and fusion and losses dissipated by bremsstrahlung, Compton,
conduction and synchrotron. We are able to construct the boundaries for
boot-strapping burn (dT/dt/spl ges/0) with or in absence (ICF) of magnetic
field. We demonstrate that MTF ignition can occur using very low implosion
velocities for plasmas with very low Rho-R and densities (by ICF standards).
This is possible because the major heat loss mechanism, thermal conduction is
suppressed by megagauss fields and the DT alpha particles are partially trapped
within the plasma. We prove, unlike ICF, that the fusion region for MTF is
sensitive to the mass of the DT in the target. This sensitivity just reflects
the fact that the additional physical processes involved in MTF don't have the
same dependence on density and target radius separately, so the the equations
don't scale in such a simple way with Rho-R. For a target containing 10 mu-gm of
DT, the MTF region is considerably smaller than for 100 mu-gm, and even the ICF
region is hardly enlarged at all.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee1912&issue=v1995i0506&article=194_mtfic
PLASMA
16. Science Server at LANL
Detailed modeling of proposed liner-on-plasma fusion experiments
Sheehey, P.T.; Faehl, R.J.; Kirkptrick, R.C.; Lindemuth, I.R.
Los Alamos Nat. Lab., NM, USA
IEEE International Conference on Plasma Science; New Orleans, LA, USA; June 4,
2000
pp. 218
Summary form only given, as follows. Magnetized target fusion (MTF) is a
potentially inexpensive approach to controlled fusion in which a preheated and
magnetized target plasma is hydrodynamically compressed by an imploding liner.
If electron thermal conduction losses are magnetically suppressed, relatively
slow O(1 cm/microsecond) "liner-on-plasma" compressions, magnetically driven
using inexpensive electrical pulsed power, may be practical. Target plasmas in
the range 1018 cm-3, 100 eV, 100 kG need to remain
relatively free of potentially cooling contaminants during formation and
compression. Magnetohydrodynamic (MHD) calculations including derailed effects
of radiation, heat conduction, and resistive field diffusion have been used to
model separate static target plasma (Russian MACO, Z-pinch, Field Reversed
Configuration) and liner implosion (without plasma fill) experiments. Using
several different codes, liner-on-plasma compression experiments are now being
modeled in one and two dimensions to investigate important issues for the design
of proposed liner-on-plasma MTF experiments. The competing processes of
implosion, heating, mixing, and cooling determine the potential for such
liner-on-plasma experiments to achieve fusion conditions.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee1912&issue=v2000i0406&article=218_dmoplfe
PLASMA
17. Science Server at LANL
Computational and experimental results of a wall-supported dense Z-pinch
experiment
Sheehey, P.T.; Kirkpatrick, R.C.; Lindemuth, I.R.; Wysocki, F.W.; Thio, Y.C.F.
Los Alamos Nat. Lab., NM, USA
IEEE International Conference on Plasma Science; Raleigh, NC, USA; June 1, 1998
pp. 322
Summary form only given. In Magnetized Target Fusion (MTF) experiments, a
preheated and magnetized target plasma is hydrodynamically compressed to fusion
conditions by a magnetically driven liner. MTF requires initial target plasma
conditions of order 1018 cm-3, 100 eV, and 100 KGauss. A
deuterium-fiber-initiated dense Z-pinch experiment to reach target plasma
conditions has been designed, modelled, and built at Los Alamos National
Laboratory (1). This experiment is unique in that it utilizes m=0 instability to
fill the 2-cm-radius plasma chamber, after which computations predict a
relatively stable wall-supported condition may be found. An important issue to
be addressed is whether or not heat loading on the walls, and high current
density loading on the electrodes of such a pinch, will result in undesirable
contamination of the plasma with high-Z material. Additions to the computational
model and experimental diagnostics are being prepared to answer such questions.
Detailed comparison of the modelling results with experiment will be presented.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee1912&issue=v1998i0106&article=322_caeroawdze
PLASMA
18. Science Server at LANL
DT alpha energy deposition in a magnetized plasma
Guerton, F.; de Peretti, M.; Sabatier, M.
Centre d'Etudes de Bruyeres-le-Chatel, France
IEEE International Conference on Plasma Science; New Orleans, LA, USA; June 4,
2000
pp. 105
Summary form only given. We present a 3D code for calculating the energy
deposited as a function of the position within the plasma, assuming an arbitrary
magnetic field configuration. This code tracks the very complex trajectories of
the alphas, tabulating the energy along the path and terminating the trajectory
when an alpha leaves the target plasma or slows to thermal velocity. The amount
of energy deposited in the plasma depends on the temperature, density and radius
of the plasma and on the strength and configuration of the field. We report some
of our particle tracking calculations and discuss various methods for handling
DT alpha energy deposition in calculations for Magnetized Target Fusion (MTF).
In this case, we show the fractional deposition, averaged over volume and angle,
in a homogeneous magnetized plasma with an azimuthal field and point up that the
important parameter for enhancement is the field times target radius. For BR>0.5
MGcm, significant enhancement occurs and for BR>5 MGcm greatly increases energy.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee1912&issue=v2000i0406&article=105_daediamp
PLASMA
19. Science Server at LANL
Computational modeling of wall-supported dense Z-pinches
Sheehey, P.T.; Gerwin, R.A.; Kirkpatrick, R.C.; Lindemuth, I.R.; Wysocki, F.J.
Los Alamos Nat. Lab., NM, USA
IEEE International Conference on Plasma Science; San Diego, CA, USA; May 19,
1997
pp. 183 - 184
Summary form only given, as follows. A new application for
deuterium-fiber-initiated Z-pinches is Magnetized Target Fusion (MTF), in which
a preheated and magnetized target plasma is hydrodynamically compressed, by a
separately driven liner, to fusion conditions. Although the conditions necessary
for a suitable target plasma-density (1018 cm-3),
temperature (100 eV), magnetic field (100 kG) are less extreme than those
required for the previous ohmically heated fusion scheme, the plasma must remain
magnetically insulated and clean long enough to be compressed by the imploding
liner to fusion conditions, e.g., several microseconds. A fiber-initiated
Z-pinch in a 2-cm-radius, 2-cm long conducting liner has been built at Los
Alamos to investigate its suitability as an MTF target plasma. Two-dimensional
magnetohydrodynamic modeling of this experiment shows early instability similar
to that seen on HDZP-II; however, when plasma finds support and stabilization at
the outer radial wall, a relatively stable profile forms and persists.
Comparison of experimental results and computations, and computational inclusion
of additional experimental details is being done. Analytic and computational
investigation is also being done on possible instability-driven cooling of the
plasma by Benard-like convective cells adjacent to the cold wall.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee1912&issue=v1997i1905&article=183_cmowdz
PLASMA
20. Science Server at LANL
Progress with developing a target for magnetized target fusion
Wysocki, F.J.; Chrien, B.E.; Idzorek, G.; Oona, H.; Whiteson, D.O.; Kirkpatrick,
R.C.; Lindemuth, I.R.; Sheehey, P.T.
Los Alamos Nat. Lab., NM, USA
IEEE International Conference on Plasma Science; San Diego, CA, USA; May 19,
1997
pp. 249
Summary form only given, as follows. Magnetized target fusion (MTF) is an
approach to fusion where a preheated and magnetized plasma is adiabatically
compressed to fusion conditions. Successful MTF requires a suitable initial
target plasma with an embedded magnetic field of at least 5 T in a
closed-field-line topology, a density of roughly 1018 cm-3,
a temperature of at least 50 eV, and must be free of impurities which would
raise radiation losses. Target plasma generation experiments are underway at Los
Alamos National Laboratory using the Colt facility; a 0.25 MJ, 2-3 μs rise-time
capacitor bank. In the first experiments, a Z-pinch is produced in a 2 cm radius
by 2 cm high conducting wall using a static gas-fill of hydrogen or deuterium
gas in the range of 0.5 to 2 torr. Follow-on experiments will use a frozen
deuterium fiber along the axis (without a gas-fill). The diagnostics include
B-dot probes, framing camera, gated OMA visible spectrometer, time-resolved
monochrometer, silicon photodiodes, neutron yield, and plasma-density
interferometer. Operation to date has been with drive currents ranging from 0.8
MA to 1.9 MA. Optical diagnostics show that the plasma produced in the
containment region lasts roughly 20 to 30 μs, and the B-dot probes show a broad
current-profile in the containment region. The experimental design and data will
be presented.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee1912&issue=v1997i1905&article=249_pwdatfmtf
PLASMA
21. Science Server at LANL
Progress with developing a target for magnetized target fusion
Wysocki, F.J.; Chrien, R.E.; Idzorek, G.; Oona, H.; Whiteson, D.O.; Kirkpatrick,
R.C.; Lindemuth, I.R.; Sheehey, P.T.
Los Alamos Nat. Lab., NM, USA
IEEE Internation Pulsed Power Conference; Baltimore, MA, USA; 1997
pp. 1393 - 1398
Magnetized target fusion (MTF) is an approach to fusion where a preheated and
magnetized plasma is adiabatically compressed to fusion conditions. Successful
MTF requires a suitable initial target plasma with an embedded magnetic field of
at least 5 T in a closed-field-line topology, a density of roughly 1018
cm-3, a temperature of at least 50 eV, and must be free of impurities
which would raise radiation losses. Target plasma generation experiments are
underway at Los Alamos National Laboratory using the Colt facility; a 0.25 MJ,
2-3 μs rise-time capacitor bank. The goal of these experiments is to demonstrate
plasma conditions meeting the minimum requirements for a MTF initial target
plasma. In the first experiments, a Z-pinch is produced inside a 2 cm radius by
2 cm high conducting cylindrical metal container using a static gas-fill of
hydrogen or deuterium gas in the range of 0.5 to 2 ton. Thus far, the
diagnostics include an array of 12 B-dot probes, a framing camera, a gated OMA
visible spectrometer, a time-resolved monochrometer, filtered silicon
photodiodes, neutron yield, and plasma-density interferometers. These
diagnostics show that a plasma is produced in the containment region that lasts
roughly 10 to 20 μs with a maximum plasma density exceeding 1018 cm-3.
The experimental design and data are presented.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee2015&issue=v1997i2906_2&article=1393_pwdatfmtf
PPC
22. Science Server at LANL
Implosion of magnetized laser targets
Gond, S.; Bourdier, A.
Dept. de Phys. Theor. et Applique, CEA, Centre d'Etudes de Bruyeres-le-Chatel,
France
IEEE International Conference on Plasma Science; New Orleans, LA, USA; June 4,
2000
pp. 141
Summary form only given, as follows. The influence of thermal conduction on
laser inertial confinement fusion is studied with a sophisticated CEA
(Commissariat a l'Energie Atomique) computer code. Our results are compared to
those previously obtained by Lindemuth and Kirkpatrick. A simple
zero-dimensional code, describing the implosion of a magnetized target is
formulated. It has been built up in order to fit as well as possible the CEA
code results in the absence of thermal conduction and when no magnetic field is
taken into account. The influence of the magnetic on the deposition of alpha
particles and the stability of such an implosion are discussed.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee1912&issue=v2000i0406&article=141_iomlt
PLASMA
23. Science Server at LANL
Comparison of Z-pinch and theta-pinch drive for implosion of solid liners
suitable for compression of Field Reversed Configurations
Degnan, J.H.; Turchi, P.J.; Siemon, R.E.
IEEE International Conference on Plasma Science; Banff, Alta., Canada; May 26,
2002
pp. 236
A comparison of Z-pinch and theta-pinch driven implosions of metal shells (solid
liners) is presented. Both schemes are feasible, and they have different
advantages for compression of magnetized plasmas to magnetized target fusion
conditions. The Z-pinch approach has already demonstrated at least 35%
conversion efficiency from stored electrical energy to implosion kinetic energy
with good implosion behavior and symmetry, and at least 13 times radial
convergence of the liner inner surface. The theta-pinch approach has potential
advantages for purer and easier injection of Field Reversed Configurations,
easier diagnostic access, and may be more easily operated repetitively.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee1912&issue=v2002i2605&article=236_cozatdfcofrc
PLASMA
24. Science Server at LANL
Method for detection and measurement of impurities in plasmas formed and
compressed to magnetized target fusion conditions
Degnan, J.H.
Air Force Res. Lab., USA
Pulsed Power Plasma Science; Las Vegas, NV, USA; June 17, 2001
pp. 536
Summary form only given. Magnetized Target Fusion (MTF) is a means to compress
plasmas to fusion conditions that uses magnetic fields to greatly reduce
electron thermal conduction, thereby greatly reducing compression power density
requirements. A principal technical risk is transport of impurities into the
plasma during formation and compression. One way to detect and measure such
impurities is to use time and space resolved vacuum ultra violet spectroscopy.
An inexpensive way to attempt this is to use arrays of silicon PIN or similar
detectors, with different filters and the use of spectrum deconvolution
techniques for time resolved spectral resolution, and to use two or more such
arrays with collimation for spatial resolution. Some analytic and numerical
studies, using a proposed array of 12 different response functions via different
filtered 250 micron thick Si PIN detectors, indicate that this approach is
feasible during compression, and perhaps prior to compression.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee2837&issue=v2001i1706&article=536_mfdamoctmtfc
PPPOS
25. Science Server at LANL
Analysis of data from Z-pinch MTF target plasma experiments
Wysocki, F.J.; Taccetti, J.M.; Gerwin, R.A.; Benage, J.F.; Idzorek, G.; Oona,
H.; Kirkpatrick, R.C.; Lindemuth, I.R.; Sheehey, P.T.
Los Alamos Nat. Lab., NM, USA
IEEE Internation Pulsed Power Conference; Monterey, CA, USA; June 27, 1999
pp. 700 - 703
The Los Alamos National Laboratory Colt facility has been used to create target
plasma for magnetized target fusion (MTF). The primary results regarding
magnetic field, plasma density, plasma temperature and hot plasma lifetime are
summarized and the suitability of these plasma targets for MTF is assessed.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee2015&issue=v1999i2706_2&article=700_aodfzmtpe
PPC
26. Science Server at LANL
Measurement of MTF target plasma temperature using filtered photodiodes
Taccetti, J.M.; Wysocki, F.J.; Idzorek, G.; Oona, H.; Kirkpatrick, R.C.;
Lindemuth, I.R.; Sheehey, P.T.
Los Alamos Nat. Lab., NM, USA
IEEE Internation Pulsed Power Conference; Monterey, CA, USA; June 27, 1999
pp. 696 - 699
Magnetized target fusion (MTF) is an approach to fusion where a preheated and
magnetized plasma is adiabatically compressed to fusion conditions. Successful.
MTF requires a suitable initial target plasma with a magnetic field of at least
5 T in a closed-field-line topology, a density of roughly 1018 cm-3,
a temperature of at least 50 eV but preferably closer to 300 eV, and must be
free of impurities which would raise radiation losses. The goal of these
experiments is to demonstrate plasma conditions meeting the requirements for an
MTF initial target plasma. The plasma is produced by driving a z-directed
current of 1-2 MA through either a static gas-fill or a 38 μm diameter
polyethylene fiber. The data obtained from an array of filtered photodiodes is
used to estimate the plasma temperature. The filter material and thickness for
each diode is chosen such that the lowest absorption edge for each is at a
successively higher energy, covering the range from a few eV to 5 keV. The
analysis assumes a fully stripped optically thin plasma which radiates as either
a blackbody, a bremsstrahlung emitter, or a group of emission lines (gaussian-like).
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee2015&issue=v1999i2706_2&article=696_momtptufp
PPC
27. Science Server at LANL
ITER and the path of minimum risk in fusion
Panarella, E.
Adv. Laser & Fusion Technol. Inc., Hull, Que., Canada
IEEE International Conference on Plasma Science; Raleigh, NC, USA; June 1, 1998
pp. 286
Summary form only given. An analysis will be presented on ITER based on heat
transfer considerations that will show the difficulties this machine will have
to reach ignition. Based on this result, it will be argued that any inertial
confinement scheme has a better chance to reach ignition. In particular, a case
will be made for the spherical pinch, or its equivalent alternate concept,
magnetized target fusion, as a scheme that offers a path of minimum risk for
ignition.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee1912&issue=v1998i0106&article=286_iatpomrif
PLASMA
28. Science Server at LANL
Measurement of MTF target plasma temperature using filtered photodiodes
Taccetti, J.M.; Wysocki, F.J.; Idzorek, G.; Oona, H.; Kirkpatrick, R.C.;
Lindemuth, I.R.; Sheehey, P.T.; Thio, F.Y.
Los Alamos Nat. Lab., NM, USA
IEEE International Conference on Plasma Science; Monterey, CA, USA; June 20,
1999
pp. 288
Summary form only given. Magnetized target fusion (MTF) is an approach to fusion
where a preheated and magnetized plasma is adiabatically compressed to fusion
conditions. Successful MTF requires a suitable initial target plasma with a
magnetic field of at least 5 T in a closed-field-line topology, a density of
roughly 1018 cm-3, a temperature of at least 50 eV but
preferably closer to 300 eV, and must be free of impurities which would raise
radiation losses. The goal of these experiments is to demonstrate plasma
conditions meeting the requirements for an MTF initial target plasma. The plasma
is produced by driving a z-directed current of 1-2 MA through either a static
gas fill or a 38 μm diameter polyethylene fiber. The data obtained from an array
of filtered photodiodes is used to estimate the plasma temperature. The filter
material and thickness for each diode is chosen such that the lowest absorption
edge for each is at a successively higher energy, covering the range from a few
eV to 5 keV. The analysis assumes a fully stripped optically thin plasma which
radiates as either a blackbody, a bremsstrahlung emitter, or a group of emission
lines (gaussian-like).
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee1912&issue=v1999i2006&article=288_momtptufp
PLASMA
29. Science Server at LANL
Characterization of a target plasma for MTF
Wysocki, F.J.; Idzorek, G.; Oona, H.; Kirkpatrick, R.C.; Lindemuth, H.; Sheehey,
P.T.; Thio, F.Y.
Los Alamos Nat. Lab., NM, USA
IEEE International Conference on Plasma Science; Raleigh, NC, USA; June 1, 1998
pp. 322 - 323
Summary form only given. Magnetized Target Fusion (MTF) is an approach to fusion
where a preheated and magnetized plasma is adiabatically compressed to fusion
conditions. Successful MTF requires a suitable initial target plasma with a
magnetic field of at least 5 T in a closed-field-line topology, a density of
roughly 1018 cm-3, a temperature of at least 50 eV but
preferably closer to 300 eV, and must be free of impurities which would raise
radiation losses. Target plasma generation experiments are performed at Los
Alamos National Laboratory using the Colt facility; a 0.25 MJ,
2.5 μs rise-time capacitor bank.
The goal of these experiments is to demonstrate plasma conditions meeting the
requirements for a MTF initial target plasma. The plasma is produced by driving
a z-directed current of 1-2 MA through either a static gas fill or a 200 μm
diameter frozen gas fiber along the axis.3 The resulting plasma is
contained in a 2 cm radius by 2 cm high cylindrical metal wall. The diagnostics
include B-dot probes, framing camera, gated OMA visible spectrometer,
time-resolved monochromator, filtered silicon photodiodes, and a plasma-density
interferometer. A multipoint Thomson scattering diagnostic is being installed,
which will use a pulsed ruby laser which produces 20 J in a 25 ns wide pulse.
The viewing optics will collect scattered light from six spatial positions in
the plasma. In addition, the background plasma light will be measured both above
and below each scattering volume to allow subtraction of this background light
from the scattered-light signal. The experimental design and data will be
presented.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee1912&issue=v1998i0106&article=322_coatpfm
PLASMA
30. Science Server at LANL
Magnetized target fusion-an overview
Kirkpatrick, R.C.
Los Alamos Nat. Lab.
IEEE International Conference on Plasma Science; Vancouver, BC, Canada; June 7,
1993
pp. 105
Summary form only given. Magnetized target fusion (MTF) consists of the
hydrodynamic compression of a wall-confined, hot, magnetized DT plasma to
ignition conditions. Even in the absence of self heating, parameter studies have
shown that targets with gains as high as ten are possible. To reduce the
radiative energy loss from the plasma so that conduction is the major energy
loss mechanism, the initial density of the DT is much lower than that used for
inertial confinement fusion (ICF). This makes the targets larger, and the
reduced losses allow a lower compression rate, so that the implosion time can be
long and the necessary power and intensity on target can be very low. The
parameter space for MTF is intermediate in density and time scales between those
of ICF and magnetic-confinement for fusion energy (MFE).
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee1912&issue=v1993i0706&article=105_mtfo
PLASMA
31. Science Server at LANL
Solid liner inner surface phenomena during compression of a field reversed
configuration plasma for a magnetized target fusion proof of principle
demonstration
Kiuttu, G.F.; Turchi, P.J.; Faehl, R.J.
US Air Force Res. Lab., Kirtland AFB, NM, USA
IEEE International Conference on Plasma Science; Monterey, CA, USA; June 20,
1999
pp. 287
Summary form only given, as follows. A proposed magnetized target fusion (MTF)
proof of principle demonstration involves compression of a field-reversed
configuration (FRC) plasma by a cylindrical, or quasi-spherical, solid liner.
Peak internal poloidal magnetic fields are anticipated to be in the range of
1-10 MG at radial compression factors of approximately 10. Several phenomena
occurring at the solid liner inner surface affect the performance of this plasma
heating and compression scheme. They include nonlinear magnetic field diffusion,
phase changes and ablation due to surface and volumetric heating, and
magnetohydrodynamic instability growth. Magnetic field diffusion limits the
magnetic field amplification and reduces the magnetic flux buffer region between
core plasma and liner. Melting and vaporization due to Joule heating alone have
been shown to be likely to occur. Evaporated liner material traveling ahead of
the liner solid surface can potentially interact deleteriously with the core
plasma before peak compression. We present results of studies of the various
phenomena using analytic models and 1- and 2-dimensional MHD simulations.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee1912&issue=v1999i2006&article=287_slispdtfpopd
PLASMA
32. Science Server at LANL
Multichord laser interferometer for the magnetized target fusion program's field
reverse configuration
Ruden, E.L.; Analla, F.T.
Naval Research Laboratory; Air Force Research Laboratory
IEEE International Conference on Plasma Science; ; May 26, 2002
pp. 270 - 270
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee1912&issue=v2002i2605&article=270_mliftmtfpfrc
33. Science Server at LANL
Numerical studies of liners for magnetized target fusion
Faehl, R.J.; Atchison, W.L.; Sheehey, P.T.; Lindemuth, I.R.
Plasma Applications Group, Los Alamos Nat. Lab., NM, USA
IEEE International Conference on Plasma Science; Monterey, CA, USA; June 20,
1999
pp. 288
Summary form only given. Magnetized target fusion (MTF) requires the fast
compression of hot, dense plasmas by a conducting liner. We have used
two-dimensional MHD calculations to study the electromagnetic implosion of
metallic liners driven by realistic current waveforms. Parametric studies have
indicated that the liner should reach velocities of 3-20 km/s, depending on the
magnetic field configuration, and reach convergence ratios (initial radius
divided by final radius) of at least 10. These parameters are accessible with
large capacitor bank power supplies such as SHIVA or ATLAS, or with magnetic
flux compression generators. One issue with the high currents that are required
to implode the liner is that Ohmic heating will melt or vaporize the outer part
of the liner. Calculations have shown that this is a realistic concern. We are
currently addressing questions of liner instability and flux diffusion under MTF
conditions. Another issue is that the magnetic fields needed to inhibit thermal
losses to the walls will also heat, melt, or vaporize the inner wall surfaces.
For initial fields between 5-50 Tesla, the wall heating is significant but does
not result in rapid melting. As the implosion evolves, flux compression leads to
fields in excess of 100 Tesla.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee1912&issue=v1999i2006&article=288_nsolfmtf
PLASMA
34. Science Server at LANL
US/Russian collaboration in high-energy-density physics using high-explosive
pulsed power: ultrahigh current experiments, ultrahigh magnetic field
applications, and progress toward controlled thermonuclear fusion
Lindemuth, L.R.; Ekdahl, C.A.; Fowler, C.M.; Reinovsky, R.E.; Younger, S.M.;
Chernyshev, V.K.; Mokhov, V.N.; Pavlovskii, A.I.
Los Alamos Nat. Lab., NM, USA
IEEE Transactions on Plasma Science ; December 1997; vol.25, no.6, pp. 1357 -
1372
A collaboration has been established between the All-Russian Scientific Research
Institute of Experimental Physics (VNIIEF) and the Los Alamos National
Laboratory (LANL), the two institutes which designed the first nuclear weapons
for their respective countries. In 1992, when emerging governmental policy in
the United States and Russia began to encourage "lab-to-lab" interactions, the
two institutes quickly recognized a common interest in the technology and
applications of magnetic flux compression, the technique for converting the
chemical energy released by high-explosives into intense electrical pulses and
intensely concentrated magnetic energy. In a period of just over three years,
the two institutes have performed more than fifteen joint experiments covering
research areas ranging from basic pulsed power-technology to solid-state physics
to controlled thermonuclear fusion. Using magnetic flux compression generators,
electrical currents ranging from 20 to 100 MA were delivered to loads of
interest in high-energy-density physics. A 20-MA pulse was delivered to an
imploding liner load with a 10-90% rise time of 0.7 μs. A new, high-energy
concept for soft X-ray generation was tested at 65 MA. More than 20 MJ of
implosion-kinetic energy was delivered to a condensed matter imploding liner by
a 100-MA current pulse. Magnetic flux compressors were used to determine the
upper critical field of a high-temperature superconductor and to create pressure
high enough that the transition from single particle behavior to quasimolecular
behavior was observed in solid argon. A major step was taken toward the
achievement of controlled thermonuclear fusion by a relatively unexplored
approach known in Russia as MAGO (MAGnitnoye Obzhatiye, or "magnetic
compression") and in the United States as MTF (Magnetized Target Fusion). Many
of the characteristics of a target plasma that produced 1013 fusion
neutrons have been evaluated. Computational models of the target plasma suggest
that the plasma is suitable for subsequent compression to fusion conditions by
an imploding pusher.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=journals&journal=00933813&issue=v25i0006&article=1357_ucihpuaptctf
35. Science Server at LANL
Joint US/Russian plasma formation experiments for magnetic
compression/magnetized target fusion
Lindemuth, I.R.; Reinovsky, R.E.; Chrien, R.E.; Christian, J.M.; Ekdahl, C.A.;
Goforth, J.H.; Haight, R.C.; Idzorek, G.; King, N.S.; Kirkpatrick, R.C.; Larson,
R.E.; Morgan, G.L.; Olinger, B.W.; Oona, H.; Sheehey, P.T.; Shlachter, J.S.;
Smith, R.C.; Veeser, L.R.; Warthen, B.J.; Younger, S.M.; Chernyshev, V.K.;
Mokhov, V.N.; Demin, A.N.; Dolin, Y.N.; Garanin, S.; Ivanov, V.A.; Korchagin,
V.P.; Mikhailov, O.D.; Morozov, I.V.; Pak, S.V.; Pavlovskii, E.S.; Seleznev,
N.Y.; Skobelev, A.N.; Volkov, G.I.; Yakubov, V.A.
Los Alamos Nat. Lab., NM, USA
IEEE Internation Pulsed Power Conference; Albuquerque, NM, USA; July 3, 1995
pp. 601 - 606
Magnetic compression/magnetized target fusion (MAGO/MTF) is an area of fusion
research that is intermediate between magnetic fusion energy (MFE) and inertial
confinement fusion (ICF) in time and density scales. In this paper, the authors
report the results of experiments exploring a scheme for forming a hot,
magnetized plasma possibly suited for subsequent implosion in a MAGO/MTF
context. The experiment described here used a copper plasma formation chamber.
The outer radius of the plasma volume was 10 cm. The chamber was initially
filled with 10 Torr of 50% deuterium, 50% tritium gas seeded with 0.01% neon for
diagnostic purposes. The chamber behavior was computationally modeled using
two-dimensional magnetohydrodynamic techniques.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee2015&issue=v1995i0307_1&article=601_jupfefmctf
PPC
36. Science Server at LANL
The magnetically driven imploding liner parameter space of the Atlas capacitor
bank
Lindemuth, I.R.; Atchison, W.L.; Faehl, R.J.; Reinovsky, R.E.
Los Alamos Nat. Lab., NM, USA
Pulsed Power Plasma Science; Las Vegas, NV, USA; June 17, 2001
pp. 1386 - 1389
The Atlas capacitor bank (23 MJ, 30 MA, 240 kV) is now operational at Los
Alamos. Atlas was designed to magnetically drive imploding liners for use as
impactors in shock and hydrodynamic experiments. We have conducted a
computational "mapping" of the high-performance imploding liner parameter space
accessible with Atlas. The effect of charge voltage, transmission inductance,
liner thickness, liner initial radius, and liner length, as well as other
parameters, has been investigated. Our study shows that Atlas is ideally suited
to be a liner driver for liner-on-plasma experiments in a magnetized target
fusion context.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee2837&issue=v2001i1706_2&article=1386_tmdilpsotacb
PPPS
37. Science Server at LANL
Magnetized target fusion
de Peretti, M.; Sabatier, M.
Centre d'Etude de Limeil-Valenton, Villeneuve St Georges, France
IEEE International Conference on Plasma Science; Boston, MA, USA; June 3, 1996
pp. 180
Summary form only given. We present a OD model (cylindrical and spherical)
describing the slow implosion of a high conducting shell surrounding a
magnetized fuel relevant of the MTF concept which take advantage of two benefits
of the magnetic field in the plasma by the reduction of: the thermal conduction
during the implosion process; the mean free path of the alpha particles during
the ignition. The shell is made up of an external incompressible fluid part and
an internal compressible dense plasma. This model permit a survey of the
parameter space available for magnetized fuel. It predicts the existence of a
new region in parameter space where significant thermonuclear fuel burn-up can
occur at very low densities, very low implosion velocities and with drive
requirements reduced by several orders of magnitude.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee1912&issue=v1996i0306&article=180_mtf
PLASMA
38. Science Server at LANL
Pre-ionization experiments on a high-density field reversed configuration
suitable for magnetized target fusion
Taccetti, J.A.; Intrator, T.P.; Wurden, G.A.; Snyder, H.R.; Tuszewski, A.;
Siemon, R.; Begay, D.; Mignardot, E.; Newton, R.; Sanchez, P.; Sandoval, G.;
Waganaar, B.; Degnan, J.H.; Sommars, W.; Grabowski, C.; Gale, D.; Cavazos, T.;
Pearson, B.
Los Alamos Nat. Lab., NM, USA
Pulsed Power Plasma Science; Las Vegas, NV, USA; June 17, 2001
pp. 535
Summary form only given. We present the progress on the high-density Field
Reversed Configuration (FRC) experiment presently being studied at LANL. This
FRC will be the target plasma for Magnetized Target Fusion (MTF) experiments;
heating it by compressing it inside an imploding flux conserver should allow
access to fusion conditions. Diagnosing the FRC plasma will be challenging due
to the short timescales, high energy densities, high magnetic fields, and
restricted access. Our goal is an FRC with n1017
cm-3, T1=Te=100-300
eV, B5 T, and a lifetime of 10-20
μs. Results to date on the Pre-Ionization (PI) phase of the experiment will be
presented. From our previous experience, the PI process is crucial for good FRC
formation, and not well understood. Initial attempts will include using the
ringing theta coil discharge (/spl theta/-PI) technique, which ionizes the gas
by impressing a rapidly oscillating (300
kHz) axial magnetic field superimposed upon the slower-timescale magnetic bias
field, of comparable magnitude. The PI process occurs just prior to applying a
much (10×) higher reverse field that causes the frozen-in field lines to
radially contract and form the closed field lines for the FRC.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee2837&issue=v2001i1706&article=535_peoahfcsfmtf
PPPOS
39. Science Server at LANL
Surface erosion instabilities driven by edge plasma
Bruskin, L.G.; Tamano, T.
Plasma Res. Center, Tsukuba Univ., Japan
7 ; February 01, 1996; vol.36, no.2, pp. 199-208
The interaction of magnetized edge plasma with the material surface in the
divertor region of a fusion device is analytically investigated. It is shown
that the process of surface erosion is unstable against small perturbations of
the surface shape, which leads to a gradual roughening of the initially smooth
target surface. Two distinct reasons are studied for possible drivers of such
erosion instabilities: modification of ion deposition flux and surface
temperature variation. The wavenumbers of the unstable perturbations are
determined from a linear approximation of the surface erosion equation. For the
plasma parameters relevant to fusion reactors the estimated mean time of surface
roughening is about a few hours. Consequently, the erosion instability is of
importance for long pulse and steady state operation of future reactor-grade
fusion devices
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=journals&journal=00295515&issue=v36i0002&article=199_seidbep
40. Science Server at LANL
Magnetized target fusion: no capital investment required!!!
Lindemuth, I.R.; Siemon, R.E.; Kirkpatrick, R.C.; Reinovsky, R.E.
Los Alamos Nat. Lab., NM, USA
IEEE International Conference on Plasma Science; Monterey, CA, USA; June 20,
1999
pp. 109
Summary form only given, as follows. The constraints of steady-state operation
for magnetic confinement and of no magnetic field for inertial confinement have
forced fusion research into two extreme corners separated by more than ten
orders of magnitude in time and density scales and requiring multi-billion
dollar capital investments for the next steps. Simple analysis shows that
combining the compressional heating of inertial confinement with the thermal
insulating properties of magnetic confinement and operating in a density and
time space intermediate between the two conventional fusion approaches leads to
a path to fusion that can be accessed by pulsed power facilities that either
already exists or are under construction in non-fusion contexts.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee1912&issue=v1999i2006&article=109_mtfncir
PLASMA
41. Science Server at LANL
Analysis of data from z-pinch MTF target plasma experiments
Wysocki, F.J.; Taccelti, J.M.; Benage, J.F.; Idzorek, G.K.; Oona, H.;
Kirkpatrick, R.C.; Lindemuth, I.R.; Sheehey, P.T.
Los Alamos Nat. Lab., NM, USA
IEEE International Conference on Plasma Science; Monterey, CA, USA; June 20,
1999
pp. 289
Summary form only given. Magnetized Target Fusion (MTF) target plasma
experiments have been performed at the Los Alamos National Laboratory Colt
facility for roughly three years. The capacitor bank has a maximum output
voltage of 120 kV, maximum energy store of 0.25 MJ, and can deliver at least 2
MA of current to a load in 2.5 microseconds. The approach for MTF target plasma
generation has been to drive a z-directed current through a plasma which is
contained by a 2 cm radius by 2 cm high cylindrical metal wall. The initial mass
for the target plasma comes from either a static uniform fill of hydrogen or
deuterium gas, or from a polyethylene fiber mounted along the central axis.
Polyethylene fibers were used as a substitute for the cryogenically frozen
deuterium fibers that were originally planned for. The diagnostic set includes
an array of 12 B-dot probes, optical framing camera, gated OMA visible
spectrometer, time-resolved monochrometer, filtered silicon photodiodes, neutron
yield, and a laser interferometer. The data obtained allows an assessment of the
plasma temperature, density, magnetization, and decay time. With this, the
suitability of these plasmas for an MTF application will be addressed.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee1912&issue=v1999i2006&article=289_aodfzmtpe
PLASMA
42. Science Server at LANL
The magnetically driven imploding liner parameter space of the Atlas capacitor
bank
Lindemuth, I.R.; Atchison, W.L.; Faehl, R.J.; Reinovsky, R.E.
Los Alamos Nat. Lab., NM, USA
Pulsed Power Plasma Science; Las Vegas, NV, USA; June 17, 2001
pp. 409
Summary form only given, as follows. The Atlas capacitor bank (23 MJ, 30 MA) is
now operational at Los Alamos. Atlas was designed primarily to magnetically
drive imploding liners for use as impactors in shock and hydrodynamic
experiments. We have conducted a computational "mapping" of the high-performance
imploding liner parameter space accessible to Atlas. The effect of charge
voltage, transmission inductance, liner thickness, liner initial radius, and
liner length has been investigated. One conclusion is that Atlas is ideally
suited to be a liner driver for liner-on-plasma experiments in a magnetized
target fusion (MTF) context . The parameter space of possible Atlas
reconfigurations has also been investigated.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee2837&issue=v2001i1706&article=409_tmdilpsotacb
PPPOS
43. Science Server at LANL
Theory and MHD simulation of fuelling by compact toroid injection
Suzuki, Y.; Hayashi, T.; Kishimoto, Y.
Plasma Theory Laboratory, Department of Fusion Plasma Research, Naka Fusion
Research Establishment, Japan Atomic Energy Research Institute, Naka, Japan;
Theory and Computer Simulation Center, National Institute for Fusion Science,
Toki, Japan
Nuclear Fusion ; July 01, 2001; vol.41, no.7, pp. 873-881
The process of fuelling by injection of a spheromak-like compact toroid (SCT) is
investigated by using MHD numerical simulations, where the SCT is injected into
a magnetized target plasma region corresponding to a fusion device. In a
previous study, the authors proposed a theoretical model to determine the
penetration depth of the SCT into the target region on the basis of simulation
results; in that study the SCT is decelerated not only by the magnetic pressure
force but also by the magnetic tension force. However, since both ends of the
target magnetic field are fixed on the boundary wall in the simulation, the
deceleration caused by the magnetic tension force would be overestimated. In the
present study, the dependence of the boundary condition of the target magnetic
field on the SCT penetration process is examined. On the basis of these results,
the theoretical model previously proposed is improved to include the effect that
the fluctuations of the target magnetic field propagate with the Alfvén
velocity. In addition, by carrying out the simulation with the torus domain, it
is confirmed that the theoretical model can be applied to estimate the
penetration depth of the SCT under such conditions. The dependence of the
injection position (side injection and top/bottom injection) on the penetration
process is also examined.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=journals&journal=00295515&issue=v41i0007&article=873_tamsofbcti
44. Science Server at LANL
MHD-nozzle device as a thermonuclear target in MAGO/MTF concept
Demin, A.N.; Chernyshev, V.K.; Korchagin, V.P.; Mokhov, V.N.; Ivanov, V.A.; Pak,
S.V.; Yakubov, V.B.; Garanin, S.F.; Mamyshev, V.I.; Kuznetsov, S.D.; Subbotin,
A.N.; Burencov, O.M.; Dolin, Y.N.; Dudin, V.I.; Morozov, I.V.; Volkov, A.A.;
Trusilo, S.V.; Usenko, P.L.; Skobelev, A.N.; Shpagin, V.I.
Sci. Res. Inst. of Exp. Phys., Nizhni Novgorod, Russia
Proceedings of the International Conference on High-Power Particle Beams; Haifa,
Israel; June 7, 1998
pp. 585 - 587
Describes the MAGO-MTF (magnetised target fusion) approach to fusion energy
using a MHD-nozzle device as the thermonuclear target. In MAGO-MTF,
thermonuclear reaction ignition has two stages: 1) heated magnetized plasma
formation; and 2) adiabatic compression of the obtained plasma and the
achievement of thermonuclear reaction burning conditions. The formation of
plasma with definite temperature and lifetime is carried out by means of plasma
acceleration up to ultrahigh velocities in the MHD Laval nozzle under the
influence of quick-increasing magnetic field pressure and by means of the
further plasma thermalisation. Some results of the MHD-nozzle device
calculations are presented, in which one can see the character of plasma motion
and the dynamics of its heating.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee1078&issue=v1998i0706_2&article=585_mdaattimc
BEAMS
45. Science Server at LANL
Two-dimensional MHD calculations of a liner compressed MTF plasma
Faehl, R.J.; Lindemuth, I.R.; Sheehey, P.T.; Kirkpatrick, R.
Appl. Theor. Phys. Div., Los Alamos Nat. Lab., NM, USA
IEEE International Conference on Plasma Science; Banff, Alta., Canada; May 26,
2002
pp. 169
Magnetized Target Fusion (MTF) is a generalized scheme for attaining burning
plasma conditions by feeding power into a dense plasma by means of a fast liner
implosion, at a rate faster than thermal transport diffuses it to the walls. The
magnetic field is critical to inhibit these thermal losses, but it is neither
intended nor needed to provide steady plasma confinement. Two-dimensional MHD
calculations have been used previously to follow the highly transient process of
injection of dense plasma into a chamber and the subsequent relaxation and decay
of this plasma. Those calculations were sufficiently promising that more
complete simulations are being performed to track the time-dependent evolution
of the target plasma during liner implosion of the configuration. Zero-dimension
studies show strong "islands" in parameter-space for which fusion conditions can
be obtained. Initial conditions of hydrogenic plasma density, 10+18
cm-3, ion temperature, 100 eV, and initial magnetic fields of 5-30 T
are typical for such islands. The issues we are attempting to elucidate with 2-D
MHD calculations are the convective stability of the plasma-wall interface, wall
heating and migration of cold wall material into the hot, dense plasma, and
ultimately the state of the full plasma system after a radial compression ratio
of 10:1. Both the static chamber walls and the imploding wall (the liner) are
treated with realistic Equations of state and electrical conductivities. The
liner implosion is driven by either existing pulsed power sources such as ATLAS
or Disk Electromagnetic Generators (DEMG), or by conservative extrapolation of
such sources. Liner stability during closure of the chamber flux/plasma input
gap by the imploding wall is also studied. Previous studies have indicated that
densities in excess of 10+20 cm-3 can be achieved, along
with temperatures greater than 1 keV.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee1912&issue=v2002i2605&article=169_tmcoalcmp
PLASMA
46. Science Server at LANL
Computational Modeling Of Magnetized Target Fusion Experiments
Havranek, J.J.; Sheehey, P.; Kirkpatrick, R.C.; Lindemuth, I.R.; Eddleman, J.L.;
Hartman, C.W.
Los Alamos National Laboratory
IEEE International Conference on Plasma Science; Santa Fe, NM, USA; June 6, 1994
pp. 223 - 223
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee1912&issue=v1994i0606&article=223_cmomtfe
PLASMA
47. Science Server at LANL
Soft X-ray diagnostics for pulsed power machines
Idzorek, G.C.; Coulter, W.L.; Walsh, P.J.; Montoya, R.R.
Los Alamos Nat. Lab., NM, USA
IEEE Internation Pulsed Power Conference; Albuquerque, NM, USA; July 3, 1995
pp. 981 - 986
A variety of soft X-ray diagnostics are being fielded on the Los Alamos National
Laboratory Pegasus and Procyon pulsed power systems and also being fielded on
joint US/Russian magnetized target fusion experiments known as MAGO (Magnitoye
Obzhatiye). We have designed a low-cost modular photoemissive detector
designated the XRD-96 that uses commercial 1100 series aluminum for the
photocathode. In addition to photocathode detectors a number of designs using
solid state silicon photodiodes have been designed and fielded. We also present
a soft X-ray time-integrated pinhole camera system that uses standard type
TMAX-400 photographic film that obviates the need for expensive and no longer
produced zero-overcoat soft X-ray emulsion film. In a typical experiment the
desired spectral energy cuts, signal intensity levels, and desired field of view
will determine diagnostic geometry and X-ray filters selected. We have developed
several computer codes to assist in the diagnostic design process and data
deconvolution. Examples of the diagnostic design process and data analysis for a
typical pulsed power experiment are presented.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee2015&issue=v1995i0307_2&article=981_sxdfppm
PPC
48. Science Server at LANL
Initial design for an experimental investigation of strongly coupled plasma
behavior in the Atlas facility
Munson, C.P.; Benage, J.F., Jr.; Taylor, A.J.; Trainor, R.J., Jr.; Wood, B.P.;
Wysocki, F.J.
Los Alamos Nat. Lab., NM, USA
IEEE International Conference on Plasma Science; Monterey, CA, USA; June 20,
1999
pp. 142
Summary form only given. Atlas is a high current (30
MA peak, with a current risetime 4.5
μsec), high energy (Estored=24 MJ, Eload=3-6 MJ), pulsed
power facility which is being constructed at Los Alamos National Laboratory with
a scheduled completion date in the year 2000. When operational, this facility
will provide a platform for experiments in high pressure shocks (>20 Mbar),
adiabatic compression (ρ/ρ0>5, P>10 Mbar), high magnetic fields (2000
T), high strain and strain rates (<IMG SRC=/images/glyphs/PGE.GIF>>200%, d<IMG
SRC=/images/glyphs/PGE.GIF>/dt104
to 106 s-1), hydrodynamic instabilities of materials in
turbulent regimes, magnetized target fusion, equation of state, and strongly
coupled plasmas. For the strongly coupled plasma experiments, an auxiliary
capacitor bank will be used to generate a moderate density (<0.1 solid),
relatively cold (1 eV) plasma by
ohmic heating of a conducting material of interest such as titanium. This target
plasma will be compressed against a central column containing diagnostic
instrumentation by a cylindrical conducting liner that is driven radially inward
by current from the main Atlas capacitor bank. The plasma is predicted (by 1-D
numerical simulations using the RAVEN and CRUNCH codes) to reach densities of
1.1 times solid, achieve ion and
electron temperatures of 10 eV, and
pressures of 4-5 Mbar. This is a
density/temperature regime which is expected to experience strong coupling (Γ14),
but only partial degeneracy (Θ0.7).
X-ray radiography is planned for measurements of the material density at
discrete times during the experiments; diamond Raman measurements are
anticipated for determination of the pressure.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee1912&issue=v1999i2006&article=142_idfaeipbitaf
PLASMA
49. Science Server at LANL
X-ray diagnostics for an MTF initial target plasma
Thio, Y.C.F.; Kirkpatrick, R.C.; Idzorek, G.C.; Wysocki, F.; Sheehey, P.;
Lindemuth, J.R.; Degnan, J.H.
Los Alamos Nat. Lab., NM, USA
IEEE International Conference on Plasma Science; Raleigh, NC, USA; June 1, 1998
pp. 323
Summary form only given. Theoretical and experimental investigations are in
progress at the Los Alamos National Laboratory (LANL) in developing a suitable
initial plasma for magnetized target fusion (MTF). Current investigation
involves the production of a plasma using a z-directed current of 1-2 MA through
either a gas fill or a 200 mm diameter frozen gas fiber along the axis. The
resulting plasma is supported by a 2 cm radius by 2 cm high metallic wall.
During the formation, the plasma is expected to have temperatures ranging from
50 eV to in excess of 500 eV, and densities in the neighborhood of 1018cm-3.
As a component of a diverse range of diagnostics fielded or to be fielded on the
experiments, the X-ray emissions from the plasma are being characterized to
provide temperature information about the plasma, using a multi-channel soft
X-ray absorption/scattering spectrometer. The X-ray emissions are first passed
through a set of filters and the resultant filtered X-rays are detected by an
array of X-ray sensitive silicon diodes. The paper will present the conceptual
design studies leading to the selection of the filters, and the analytical
techniques for deconvoluting the X-ray data. The design studies involve the
simulation of the diode response to X-ray emissions from hypothetical
temperature and density profiles in the plasma, and also sensitivity studies on
the capability of the spectrometer to resolve the emissions from possible
impurities, Preliminary indications of the temperature obtained in plasmas
formed in experiments using gas fill will also be presented.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee1912&issue=v1998i0106&article=323_xdfamitp
PLASMA
50. Science Server at LANL
Ignition conditions for magnetized target fusion in cylindrical geometry
Basko, M.M.; Kemp, A.J.; Meyer-ter-Vehn, J.
Département de Recherches sur la Fusion Controlée, CEA Cadarache, St. Paul-lez-Durance,
France; Max-Planck-Institut für Quantenoptik, Garching, Germany
Nuclear Fusion ; January 01, 2000; vol.40, no.1, pp. 59-68
Ignition conditions in axially magnetized cylindrical targets are investigated
by examining the thermal balance of assembled DT fuel configurations at
stagnation. Special care is taken to adequately evaluate the energy fraction of
3.5 MeV alpha particles deposited in magnetized DT cylinders. A detailed
analysis of the ignition boundaries in the ρR,T parametric plane is presented.
It is shown that the fuel magnetization allows a significant reduction of the ρR
ignition threshold only when the condition BR >rsim; 6 × 105G cm is
fulfilled (B is the magnetic field strength and R is the fuel radius).
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=journals&journal=00295515&issue=v40i0001&article=59_icfmtficg
51. Science Server at LANL
Progress on formation of field reversed configurations suitable for subsequent
compression to magnetized target fusion conditions
Degnan, J.H.; Hussey, T.W.; Kiuttu, G.F.; Lehr, F.M.; Peterkin, R.E., Jr.;
Ruden, E.L.; Cavazos, T.; Gale, D.; Gilman, C.; Grabowski, C.; Sommars, W.;
Coffey, S.K.; Frese, M.; Marklin, G.; Faehl, R.J.; Intrator, T.P.; Kirkpatrick,
R.; Lindermuth, I.; Moses, R.; Schoenberg, K.F.; Siemon, R.E.; Taccetti, J.M.;
Turchi, P.J.; Wurden, G.A.; Roderick, N.F.
Pulsed Power Plasma Science; Las Vegas, NV, USA; June 17, 2001
pp. 594
Summary form only given. The design, calculations, and experimental progress on
forming Field Reversed Configuration's (FRCs) suitable for subsequent
compression by an imploding metal liner to Magnetized Target Fusion (MTF)
conditions are presented and discussed. The desired initial FRC parameters are
density 1017 cm-3,
temperature 100 to 300 eV, length
30 cm, separatrix radius
2.5 cm, magnetic field between
separatrix and liner 5 Tesla. This
effort is being pursued using the 36 mf, 250 kilojoule Colt capacitor bank at
LANL, and using the 110 mf, 750 kilojoule formation capacitor bank (FB), which
is auxiliary to the 1300 mf, 9 megajoule Shiva Star capacitor bank at AFRL, as
well as smaller auxiliary banks to drive smaller, related solenoids. Crowbarring
of both the Colt and FB facilities will be done, using triggered pressurized
railgap switches. Initial FRC diagnostics include laser interferometry and
magnetic field probe arrays (to observe field exclusion, that is, diamagnetic
effect). Later experiments will include spectroscopy for impurity detection and
temperature measurement, and Thompson scattering. The 30 cm long, 5 cm initial
radius, 0.11 cm thick Al liner is imploded by magnetic pressure from an 11
megamp axial discharge driven by the 1300 mf Shiva star capacitor bank. Initial
successful implosions are reported Transactions on Plasma Science (Degnan,
2001). Other aspects of FRC formation and compression were discussed by K.
Schoenberg, R. Siemon et al. (1998). 2D-MHD simulations of planned FRC formation
are also presented. These predict that with 100 milliTorr deuterium gas prefill,
which corresponds to 6×1015
cm-3 initial ion/atomic density,
0.5 Tesla initial bias axial
magnetic field, and 3 ms risetime,
5 Tesla reverse bias field, that the desired density and temperature FRC is
formed.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee2837&issue=v2001i1706&article=594_pofofrctmtfc
PPPOS
52. Science Server at LANL
Magnetic diffusion in conductors at ultrahigh current density
Sharp, G.T.
Pulsed Power Plasma Science; Las Vegas, NV, USA; June 17, 2001
pp. 211
Summary form only given. Recent experiments on the Z-Accelerator at Sandia
National Laboratories were performed to characterize magnetic diffusion in
aluminum and copper at currents of 3-4MA/cm and pulsewidths of 200ns. Principal
diagnostics include a unique type of B-dot probe and VISAR laser interferometry.
Streak camera spectroscopy and pyrometry were also fielded on representative
shots. These experiments were designed to allow comparison between magnetic
field diffusion rate and the pressure wave propagation resulting in the onset of
motion. As the magnetic field diffuses into the conductive material the current
causes joule heating which changes both the thermal and electrical conductivity
of the material resulting in energy losses. These nonlinear effects are not well
known at these current densities Magnetic diffusion and energy deposition are
important in several areas including the following. First, it is desirable to
understand the losses associated with magnetic diffusion for the upward power
scaling of the next generation Z-Accelerator, and to characterize potential
construction materials. Second, it is necessary to understand the rate of
magnetic diffusion when designing isentropic compression experiments on solids
such that materials and sample thickness can be selected in order to study
pressure wave loading and unloading without the confounding effects of magnetic
diffusion. Third, there is an ongoing push to improve the predictive
capabilities of magnetohydrodynamic (MHD) codes such as MACH2 and Alegra in
order to more accurately model experiments in this current density regime.
Fourth, several groups are interested in understanding the physics of exploding
wires driven by very high currents. And finally, several other groups are
interested in magnetized target fusion, which incorporates driven aluminum
liners used to compress a plasma in a field reversed configuration.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee2837&issue=v2001i1706&article=211_mdicaucd
PPPOS
53. Science Server at LANL
Implosion de cibles laser magnétisées: influence de la limitation du flux
thermique
Gond, Sylvia; Bourdier, Alain
Département de physique théorique et appliquée, Direction Île-de-France,
Commissariat à l'énergie atomique, BP 12, 91680 , Bruyères le Châtel, France
Comptes Rendus de l Academie des Sciences Series IV Physics ; May, 2000; vol.1,
no.4, pp. 509-515
The influence of thermal conduction on laser inertial confinement fusion is
studied with a sophisticated CEA (Commissariat à l'Énergie Atomique) computer
code. The beneficial effect of magnetic field on gain, shown by I.R. Lindemuth
and R.C. Kirkpatrick, is qualitatively confirmed by our results.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=journals&journal=12962147&issue=v01i0004&article=509_idclmidlldft
54. Science Server at LANL
Modeling of MAGO plasma compression by imploding liner
Buyko, A.M.; Garanin, S.F.; Ivanova, G.G.; Kuznetsov, S.D.; Mamyshev, V.I.;
Sofronov, V.N.; Yakubov, V.B.
All-Russian Res. Inst. of Exp. Phys., Nizhni Novgorod, Russia
IEEE Internation Pulsed Power Conference; Monterey, CA, USA; June 27, 1999
pp. 1052 - 1055
Magnetized plasma with characteristic density 8·1017 cm-3
and average temperature 250 eV has been obtained in a MAGO plasma chamber. One
and two dimensional magneto-hydrodynamic computations are performed in which a
solid density aluminum liner is imploded on the MAGO target plasma. An influence
of a liner compressibility, 2-dimensional effects and various heat losses on the
compressed plasma parameters are studied. The computations demonstrate that for
a liner energy that has already been achieved experimentally the compressed
plasma parameters can meet the Lawson criterion and this plasma can provide a
large amount of neutrons and X-ray radiation.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee2015&issue=v1999i2706_2&article=1052_mompcbil
PPC
55. Science Server at LANL
Magnetized cylindrical targets for heavy ion fusion
Kemp, A.J.; Basko, M.; Meyer-ter-Vehn, J.
Max-Planck-Institut für Quantenoptik, Hans-Kopfermann-Str. 1, 85748 , Garching,
Germany; Institute for Theoretical and Experimental Physics, B.
Cheremushkinskaya 25, 117259 , Moscow, Russia
Nuclear Instruments and Methods in Physics Research Section A: Accelerators,
Spectrometers, Detectors and Associated Equipment ; May 21, 2001; vol.464,
no.1-3, pp. 192-195
Ignition conditions for magnetized cylindrical fusion targets are investigated
by means of one-dimensional hydrodynamic calculations. Of particular interest is
the effect of a tamper surrounding the fuel at the time of stagnation. The key
assumption in this paper is that the targets are magnetically insulated, i.e.
electronic and ionic heat conduction as well as the diffusion of 3.5MeV alpha
particles are suppressed. It is found that magnetically insulated targets can be
ignited at significantly reduced values of the fuel ρR, but, in contrast
to conventional fusion targets, the value of the fuel ρR at ignition
depends on the fuel mass as well as on the tamper entropy.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=journals&journal=01689002&issue=v464i1-3&article=192_mctfhif
56. Science Server at LANL
Plasma Formation Experiments Relevant To Magnetized Target Fusion
Lindemuth, I.R.; Anderson, B.; Canada, J.; Chrien, R.; Ekdahl, C.; Findley, C.;
Goforth, J.; Kirkpatrick, R.; Oona, H.; Reinovsky, R.; Rodriguez, P.; Shechey,
P.; Shlachter, J.; Smith, R.; Stradling, G.; Thurston, R.; Chernyshev; Dolin,
V.N.; Gararrin, S.F.; Korchagin, V.P.; Mokhov, V.N.; Morozov, I.V.; Pak, S.V.;
Pavlovskii, E.S.; Volkov, G.I.
Los Alamos National Laboratory
IEEE International Conference on Plasma Science; Santa Fe, NM, USA; June 6, 1994
pp. 105 - 105
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee1912&issue=v1994i0606&article=105_pfertmtf
PLASMA
57. Science Server at LANL
Progress in development of theta pinches for formation of field reversed
configurations suitable for subsequent compression to magnetized target fusion
conditions
Degnan, J.H.; Barnes, D.C.; Cavazos, T.; Coffey, S.K.; Faehl, R.J.; Frese, M.;
Gale, D.; Hussey, T.W.; Intractor, T.P.; Kirpatrick, R.; Kiuttu, G.F.; Lehr, F.M.;
Letterio, J.D.; Lindemuth, I.; Moses, R.; Peterkin, R.E.; Roderick, N.F.; Ruden,
E.L.; Schoenberg, K.; Siemon, R.E.; Sommars, W.; Turchi, P.J.; Wurden, G.A.;
White, R.; Wyosocki, F.
IEEE International Conference on Plasma Science; ; June 4, 2000
pp. 258 - 258
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=confs&journal=ieee1912&issue=v2000i0406&article=258_pidotpctmtfc
58. Science Server at LANL
Magnetized target fusion in cylindrical geometry
Basko, M.M.; Churazov, M.D.; Kemp, A.; Meyer-ter-Vehn, J.
Institute for Theoretical and Experimental Physics, B. Cheremushkinskaya 25,
117259 , Moscow, Russia
Nuclear Instruments and Methods in Physics Research Section A: Accelerators,
Spectrometers, Detectors and Associated Equipment ; May 21, 2001; vol.464,
no.1-3, pp. 196-200
General ignition conditions for magnetized target fusion (MTF) in cylindrical
geometry are formulated. To attain an MTF ignition state, the deuterium–tritium
fuel must be compressed in the regime of self-sustained magnetized implosion (SSMI).
We analyze the general conditions and optimal parameter values required for
initiating such a regime, and demonstrate that the SSMI regime can already be
realized in cylindrical implosions driven by
100kJ beams of fast ions.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=journals&journal=01689002&issue=v464i1-3&article=196_mtficg
59. Science Server at LANL
Boosting the specific impulse of high explosives by thermonuclear
microexplosions ignited with the high explosives
Winterberg, F.
University of Nevada, Reno, Dept of Physics/220, College of Arts & Sciences,
Reno, NV 89557-0058, USA
Acta Astronautica ; October, 1998; vol.43, no.7-8, pp. 437-439
The energy of a few 106 J, required to ignite a DT thermonuclear
microexplosion, is really not very large. The problem is that it must be
delivered to a target with a cross section less than 1cm2 in less
than 10 nanoseconds, which can be done with lasers or particle beams in one
step. By contrast, thermonuclear microexplosion ignition by a high explosive is
achieved in two steps: First, the chemical energy ignites a magnetized fusion
target with the energy released from this booster target igniting a second stage
high gain high yield fusion or fission–fusion target. If ignited, a DT
thermonuclear microexplosion can release an energy in excess of 109
J, or more than 1 ton of a chemical
high explosive, but 80% of this energy goes into energetic neutrons. Therefore,
to make full use of the fusion energy released into neutrons, the burnt
explosive must form a layer surrounding the microexplosion, thick enough to
absorb the neutrons, adding the nuclear energy released to the chemical energy
of the high explosive. If, for example, about 100 times more energy is released
in the microexplosion compared with the chemical energy stored in the high
explosive, the specific impulse of the combined chemical-nuclear explosion would
be increased 10 fold.</fm>
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=journals&journal=00945765&issue=v43i7-8&article=437_btsiohmiwthe
60. Science Server at LANL
Magnetized deuterium targets in heavy ion fusion
Churazov, M.D.; Sharkov, B.Yu.; Zabrodina, E.A.
Institute for Theoretical and Experimental Physics, B. Cheremushkinskaya 25,
117259 Moscow, Russia
Fusion Engineering and Design ; November, 1996; vol.32-33, no.1-4, pp. 577-584
The existence of a wave of D0.9 3He0.1
thermonuclear burning in the magnetized plasma channel is discussed. Possible
ways of carrying out experimental studies of burning wave and magnetic
insulation effects are considered.
http://sciserver.lanl.gov:80/cgi-bin/sciserv.pl?collection=journals&journal=09203796&issue=v32-33i1-4&article=577_mdtihif
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OTHER LISTINGS:
First Author:
AlexeffDate: 91,1,1
Author List: I. Alexeff, M. Rader
Citation: Proc. 1991 IEEE Int. Conf. on Plas. Science, Paper SP19
Title:
Abstract:
First Author: Alikhanov
Date: 78,1,21
Author List: Alikhanov, S.G.; Glushkov, I.S.
Citation: Dokl. Akad. Nauk SSSR; 226, 21 Jan 1976; pp. 547-549
Title: Stationary quenching wave in magnetized plasma
Abstract: The interaction of a magnetized hot plasma wete > ~ 1 with cold plasma or a gas leads to the appearance of a cooling wave. The transition layer between hot and cold plasma is the main source of radiation losses which should be compensated by a heat flow from the hot region. A stationary state is considered, equations are written in the system in which temperature and magnetic field profiles are steady, and the plasma flux with magnetic field passes through the cooling wave. Calculations, have been carried out on a computer. The dependence of the magnetized plasma flux velocity Vr on the ratio p/Hr is shown, where p is the pressure, Hr is the magnetic field in the hot reqion. The dependence of the characteristic dimension of the cooling wave on the magnetic field is determined for the hot plasma region. A considerable fraction of the rediation losses is shown to fall to the region of wete < or ~ 1.
First Author: Alikhanov
Date: 74,4,1
Author List: S.G. Alikhanov, I.K. Konkashbaev
Citation: Nuclear Fusion 14, pp. 341-343 (1974)
Title: Dynamics of an axially wall-limited theta pinch compressed by a metallic liner
Abstract: Axial plasma flow during compression of a limited theta pinch have been determined. An approximate formula for the temperature dependence on the compression ratio is compared with the results of an exact numerical calculation.
First Author: Bangerter
Date: 77,11,9
Author List: R.O. Bangerter D.J. Meeker
Citation: Presented at the 2nd Int. Topical Conf. on High Power Electron and Ion Beam Research and Technology, Ithaca, NY, Oct. 3-5, 1977, UCRL-79875, CONF-771035-15
Title: Charged particle fusion targets
Abstract: The power, voltage, energy and other requirements of electron and ion beam fusion targets are reviewed. Single shell, multiple shell and magnetically insulated target designs are discussed. Questions of stability are also considered. In particular, it is shown that ion beam targets are stabilized by an energy spread in the ion beam.
First Author: Barnes
Date: 97,4,1
Author List: D. C. Barnes
Citation: Los Alamos National Laboratory report LA-UR-96-2656 to be published in Comments on Plasma Phys. and Controlled Fusion 18(3) (1997
Title: Scaling relations for high-gain, magnetized target fusion systems
Abstract: Scenarios for high-gain, magnetized target fusion (MTF) systems are considered. As in inertial confinement fusion (ICF), MTF heats and confines plasma by spherical implosion of a (relatively) massive wall. In contrast to ICF, MTF implosion velocities are significantly reduced, with correspondingly reduced density and drive requirements. Thermal losses of the wall-confined plasma are inhibited by a strong magnetic field. As in ICF, high gain may result if a central hot plasma produces sufficient fusion power to heat additional fuel during the wall dwell time. Conventional burn propagation is practically impossible for MTF. High-gain can result only by refueling the hot plasma if a minimum rr2 is achieved (r hot plasma density, r compressed radius). This condition, which is related to the Lawson criterion, requires rana > 700m2/s (ra initial target radius, na implosion velocity). Then MTF gain is order 1000 and the yield will be large (~10GJ).
First Author: Braginskii
Date: 75,1,1
Author List: S.I. Braginskii
Citation: Rev. Plas. Physics 1 (Consultants Bureau, NY, 1965) pp. 205-311
Title: Transport processes in a plasma
Abstract: (none)
First Author: Call
Date: 89,10,2
Author List: C. J. Call, R. W. Moir
Citation: Nucl. Science & Engineering 104, 364-373 (1990)
Title: A novel fusion power concept based on molten-salt technology: PACER revisited
Abstract: Modifications to an old concept for using peaceful nuclear explosions to achieve practical fusion power are discussed. With this concept, useful energy and materials are obtained by repetitively setting off nuclear explosions in an underground cavity. This proposal, which is based on molten-salt technology, involves two modifications: (1) line the cavity with steel to make it engineerable and predictable rather than relying on an unsupported earthen cavity such as a cavity excavated in a salt dome and (2) use molten salt rather than steam. More than 70% of the energy released is then absorbed by liquid-salt evaporation, and the pressure to be contained for a given yield can be reduced by a factor of 3 or more. These modifications result in several improvements in the safety and feasibility of the contained fusion concept: (1) the tritium produced, being insoluble in the molten salt, can easily be pumped away and purified when all the vaporized salt condenses, rather than being mixed with steam; (2) the tritium inventory is substantially reduced, effectively reducing the large hazard in case of accidental venting to the atmosphere; and (3) reducing the yield used in the older studies could reduce the cost of the cavity considerably. These improvements may make the concept practical today, and a reexamination of the concept appears in order.
First Author: Chang
Date: 78,2,7
Author List: J. Chang, M.M. Widner, A.V. Farnsworth, Jr., R.J. Leeper, T.S. Prevender, L. Baker, J.H. Olsen
Citation: Proc. of the Topical Meeting on Inertial Confinement Fusion, February 7-9, 1978, San Diego, California
Title: Neutron production from advanced RDB fusion targets
Abstract: Experiments have been performed in which plastic shells, containing a CD2 fuel wire, were irradiated and imploded by a single beam from the Rehyd REB accelerator (1 MeV, 250 kA, 100 nsec). The fuel wire is pre-exploded by beam prepulse, providing preheat and magnetic fields in the fuel which permit high fuel temperatures upon implosion. Initial results indicate that greater than 106 neutrons, of energy 2.5 ± 0.2 MeV, were produced during the last 30 nsec of the voltage pulse, consistent with the expected implosion time. Additional ''null'' shots with portions of the target cut away and/or without prepulse did not produce such neutrons. These initial data suggest the origin of the neutrons to be thermonuclear.
First Author: Chu
Date: 73,4,25
Author List: M. S. Chu
Citation: Phys. of Fluids 16 (9), Sept. 1973, pp. 1441- 1445
Title: Hot plasma in contact with a cold wall
Abstract: The effect of a cold wall on a hot plasma with initial uniform temperature and strong magnetic field parallel to the wall is studied. For physical values of thermal conductivity, resistivity, and electron-ion equilibration coefficients, the full set of one-fluid, two-temperature equations is solved numerically. These results are then compared with analytic self-similar solutions. The dynamic behavior of the plasma is presented. The total energy loss to the wall per unit area is evaluated and may be approximated rather well by an analytical expression derived from the fundamental equations.
First Author: Commisso
Date: 79,8,6
Author List: Commisso, R.J.; Siemon, R.E.; McKenna, K.F.; Ekdahl, C.A.;
Bartsch, R.R.
Citation: Phys. Rev. Lett., 43 (6), 6 Aug. 1979, pp. 442-445
Title: Energy- and particle-confinement properties of an end-plugged, linear, theta pinch
Abstract: Experiments show that axial confinement of plasma in a straight theta-pinch solenoid is improved by placing solid lithium deuteride plugs at the ends. The energy confinement is increased nearly threefold in agreement with theoretical estimates which assume classical electron thermal conduction and no convective losses. The confinement of deuterium ions is explained by classical Coulomb collisions in the ablated lithium deuteride plasma.
First Author: Commisso
Date: 77,1,24
Author List: Commisso, R.J.; Quinn, W.E.; McKenna, K.F.; Freese, K.B.; Ekdahl, C.A.
Citation: Phys. Rev. Lett., 39 (3), 18 Aug. 1977, pp. 137-139
Title: Solid-end-plug experiment on a theta pinch
Abstract: Results from the first end-stopping experiment on a high-energy (TI ~ 1.5 keV, n ~ 1016 cm-3) q pinch are reported. The experiment was done with quartz end plugs. The results show that the insertion of the plugs improves plasma stability, reduces particle end loss out of the device, and improves the energy confinement.
First Author: Dawson
Date: 76,1,1
Author List: Dawson, J.M.; Rosen, B.; Okuda, H.; Alder, B.; Rotenberg, M.; Fernbach, S
Citation: Methods in Computational Physics. Advances in Research and Applications 16, (1976), pp. 281-325
Title: Collective transport in plasmas
Abstract: (none)
First Author: Drake
Date: 96,3,4
Author List: R.P. Drake, J.H. Hammer, C.W. Hartman, L.J. Perkins, D.D. Ryutov
Citation: Fusion Tech. 30, (1996), pp. 310-325
Title: Submegajoule liner implosion of a closed field line configuration
Abstract: Adiabatic compression of a preformed closed field line configuration by an imploding liner is considered. Three configurations are discussed: the field-reversed configuration, the spheromak, and the Z-pinch. It is shown that by employing a two-dimensional compression, one can reach a breakeven condition with an energy input into the plasma as low as 100 kJ. Typical initial dimensions of the liner are length, 5 to 6 cm; radius, ~ 1 cm; and wall thickness, ~0.01 cm. Liner mass is in the range of a few grams. It is assumed that the initial plasma beta is of the order of unity; in this case, the final beta is much greater than 1, and the plasma is in a wall confinement regime. Typical plasma parameters for the final state (for the linear compression ratio equal to 10) are density. 1021 cm-3; temperature, 10 keV; and magnetic field, 107 G. A brief discussion of various phenomena affecting the wall confinement is presented (magnetic field diffusion, radiative losses, and impurity penetration); the conclusion is drawn that the heat losses to the walls are modest and are not a factor that limits plasma enhancement Q. It is shown that at least for relatively thin liners, whose compressibility can be neglected, what limits Q is a relatively short liner dwell time near the maximum compression point. The scaling law for the Q versus the input parameters of the system is derived, which shows a relatively weak dependence of Q on the input energy. Possible ways for increasing the dwell time are discussed. Reactor potentialities of the system are briefly described. It is emphasized that the possibility of performing crucial experiments on small-to medium-scale experimental devices may considerably shorten the development path for the system under consideration. Some nonfusion applications of the system described are mentioned. Among them are burning and transmutation of long-lived fusion products, medical isotope production, a pulsed source of hard X rays, and fusion neutrons.
First Author: Farnsworth
Date: 78,2,7
Author List: A.V. Farnsworth, Jr., M. M. Widner, J. Chang, R.J. Leeper, L. Baker,J.N. Olsen
Citation: Proc. of the Topical Meeting on Inertial Confinement Fusion, February 7-9, 1978, San Diego, California, SAND-77-1640C; CONF-780202-17
Title: Particle beam targets containing preheated fuel and magnetic fields
Abstract: (none)
First Author: Feinberg
Date: 76,1,1
Author List: B. Feinberg
Citation: Plasma Physics 18, (1976), pp. 265-275
Title: An experimental study of hot plasma in contact with a cold wall
Abstract: An experimental study has been made of the interaction (heat transfer and wall surface damage) of a hot (T ~ 5 x 106 8K), dense (n ~1016 cm-3) deuterium plasma containing a strong magnetic field (b ~104 G) brought into sudden contact with a cold wall. The energy flux from this high b(b ~ 1) plasma to the wall was measured using a thin film, fast rise-time bolometer. The measured energy flux is found to be about that predicted by classical theory. The measured plasma transverse thermal conductivity exhibits the functional dependence on temperature, magnetic field, and density that is expected from classical theory. The extent of damage to the cold wall surface was measured using a scanning electron microscope to examine various wall samples exposed to the plasma. The observed surface damage to a copper wall sample was in reasonable agreement with the predicted damage due to sputtering. The damage to the surface of a 304 austenitic stainless steel wall sample was considerably greater than predicted by sputtering.
First Author: Gerwin
Date: 79,1,1
Author List: Gerwin, R.A.; Malone, R.C
Citation: Nucl. Fusion 19 (2),(1979), pp.155-177
Title: Adiabatic plasma heating and fusion-energy production by a compressible fast liner
Abstract: Adiabatic plasma heating by the implosion of a compressible, cylindrical, end-plugged liner is studied by means of an approximate analytical model and by a computer code that employs sophisticated equation-of-state tables for the metal liner. The model contains cylindrical convergence effects and an approximate but realistic equation-of-state. Analytic expressions are derived for the pressure profile in the liner, for the internal energy of the liner, for the maximized fusion energy output of the enclosed D-T plasma, for the corresponding optimized initial conditions, and for the resulting peak pressure, final radius and thickness, and burn time. In this idealized model that ignores losses, energy transfer efficiencies (liner to plasma) of 70% are found, and a gain of 4 (ratio of fusion energy to liner energy) can occur with an initial liner energy of 300MJm-1. Finally, losses from the plasma are briefly discussed.
First Author: Golberg
Date: 93,4,1
Author List: Gol'berg, S.M.; Velikovich, A.L.
Citation: Physics of Fluids B 5 (4) (United States), April 1993, pp.1164-1172
Title: Suppression of Rayleigh-Taylor instability by the snowplow mechanism
Abstract: Rayleigh-Taylor instability developing in a layer of matter accelerated by the pressure of magnetic field or of a light fluid is shown to be suppressed if the accelerated layer scoops unperturbed matter, entraining it into motion. This stabilizing mechanism is effective for plasma focus devices, multicascade systems like magneto-cumulative (MC) generators of high-pulsed magnetic fields or multiple gas-puff Z pinches, for impact acceleration of thin foils by high-velocity plasma clouds. Linear stability analysis of one-dimensional solutions of the piston problem demonstrates that perturbation of the given wavelength l does not grow appreciably until the thickness of the accelerated layer L(t) exceeds l. Before that, if acceleration is increased rapidly enough, amplitudes of the long-wavelength perturbations remain almost constant. If acceleration is increased not too rapidly, stays constant, or is decreased, then the long-wavelength perturbations with l > 2L(t) are damped.
First Author: Hoffman
Date: 93,3,1
Author List: A. L. Hoffman, G. A. Wurden, R. Maqueda, J. T. Slough, R. D. Milroy, J. L. McNeil, K. F. McDonald, T. E. DeHart, D. G. Harding, E. A. Crawford, L. N. Carey
Citation:Fusion Technology 23(2), 185-207 (1993)
Title:The large-s FRC experiment (LSX)
Abstract: The Large-s Experiment (LSX) was built to study the formation and equilibrium properties of field-reversed configurations (FRCs) as the scale size increases. The dynamic, field-reversed theta-pinch method of FRC creation produces axial and azimuthal deformations and makes formation difficult, especially in large devices with large s (number of internal gyroradii) where it is difficult to achieve initial plasma uniformity. However, with the proper technique, these formation distortions can be minimized and are then observed to decay with time. This suggests that the basic stability and robustness of FRCs formed, and in some cases translated, in smaller devices may also characterize larger FRCs. Elaborate formation controls were included on LSX to provide the initial uniformity and symmetry necessary to minimize formation disturbances, and stable FRCs could be formed up to the design goal of s = 8. For x {le} 4, the formation distortions decayed away completely, resulting in symmetric equilibrium FRCs with record confinement times up to 0.5 ms, agreeing with previous empirical scaling laws ({tau}{proportional_to}sR). Above s = 4, reasonably long-lived (up to 0.3 ms) configurations could still be formed, but the initial formation distortions were so large that they never completely decayed away, and the equilibrium confinement was degraded from the empirical expectations. The LSX was only operational for 1 yr, and it is not known whether s = 4 represents a fundamental limit for good confinement in simple (no ion beam stabilization) FRCs or whether it simply reflects a limit of present formation technology. Ideally, s could be increased through flux buildup from neutral beams. Since the addition of kinetic or beam ions will probably be desirable for heating, sustainment, and further stabilization of magnetohydrodynamic modes at reactor-level s values, neutral beam injection is the next logical step in FRC development. 24 refs., 21 figs., 2 tabs
First Author: Ichimaru
Date: 73,1,1
Author List: S. Ichimaru
Citation: W. A. Benjamin, Inc., Reading, MA, 1973)
Title: Basic principles of plasma physics, a statistical approach
Abstract: (book)
First Author: Jones
Date: 86,2,1
Author List: Jones, R.D.; Mead, W.C.
Citation: Nucl. Fusion 26 (2), Feb. 1986, pp.127-137
Title: Physics of burn in magnetized deuterium-tritium plasmas: spherical geometry
Abstract: There is a large region of density-temperature space in which the effects of a magnetic field on heat transport and alpha-particle mobility are significant and the magnetic pressure is small compared with the pressure of a deuterium-tritium plasma. Spherical fusion burn in this regime is examined. It is found that for volume burn, magnetic fields can greatly increase the yield. In regimes where propagating burn does not occur, the burn can be enhanced by a magnetic field. In regimes where propagating deflagration would normally occur in the absence of a magnetic field, magnetic fields actually degrade the cross-field propagation. A detonation wave is harder to ignite in the presence of a magnetic field. Once a detonation wave is ignited, no change in the propagation speed is produced by applying a magnetic
field.
First Author: Kadomtsev
Date: 92,1,1
Author List: B.B. Kadomtsev
Citation: Translation editor, Professor E. W. Laing, Institute of Physics Publishing, Bristol and Philadelphia (1992)
Title: Tokamak plasma: a complex physical system
Abstract: (none)
First Author: Kirkpatrick
Date: 91,12,1
Author List: R.C. Kirkpatrick, I.R. Lindemuth
Citation: Fusion Technology 20, (Dec. 1991)
Title: Ignition and burn in inertially confined magnetized fuel
Abstract: At the third International Conference on Emerging Nuclear Energy Systems, we presented computational results which suggested that ``breakeven'' experiments in inertial confinement fusion (ICF) may be possible with existing driver technology. We recently used the ICF simulation code LASNEX to calculate the performance of an idealized magnetized fuel target. The parameter space in which magnetized fuel operates is remote from that of both ``conventional'' ICF and magnetic confinement fusion devices. In particular, the plasma has a very high b and is wall confined, not magnetically confined. The role of the field is to reduce the electron thermal conductivity and to partially trap the DT alphas. The plasma is contained in a pusher which is imploded to compress and adiabatically heat the plasma from an initial condition of preheat and pre-magnetization to the conditions necessary for fusion ignition. The initial density must be quite low by ICF standards in order to insure that the electron thermal conductivity is suppressed and to minimize the generation of radiation from the plasma. Because the energy loss terms are effectively suppressed, the implosion may proceed at a relatively slow rate of about 1 to 3 cm/ms. Also, the need for low density fuel dictates a much larger target, so that magnetized fuel can use drivers with much lower power and power density. Therefore, magnetized fuel allows the use of efficient drivers that are not suitable for laser or particle beam fusion due to insufficient focus or too long pulse length. The ignition and burn of magnetized fuel involves very different dominant physical processes than does ``conventional'' ICF. The fusion time scale becomes comparable to the hydrodynamic time scale, but other processes that limit the burn in unmagnetized fuel are of no consequence. The idealized low gain magnetized fuel target presented here is large and requires a very low implosion velocity. 11 refs.
First Author: Kirkpatrick
Date: 81,1,1
Author List: R.C. Kirkpatrick
Citation: Nuclear Fusion 21 (11), (1981)
Title: Ignition critical profiles for small fusion targets
Abstract: To determine the minimum conditions necessary for ignition in a small fusion target, ignition critical profiles have been calculated for a static, isobaric DT plasma filling a spherical cavity which has a specified wall temperature. The results indicate that a minimum value of the product of pressure and radius PR @ to 4 x 106 Mb·mm is required for ignition, and that the value increases as the radiation temperature decreases. The limiting value of an effective areal density derived here is smaller than previous crude estimates of a minimum rR based on large laser fusion simulation codes, notwithstanding the fact that the plasma temperature q is nowhere less than the wall temperature qr. Arguments are presented which suggest that the minimum PR criterion derived here should apply crudely to the case of ignition by collapse of a single strong shock. A surprising result is suggested for this dynamic case: the initial value of PR must exceed about 2 x 105·Mbmm, compared with less than 1000 Mb·mm for DT compressed adiabatically one-thousand-fold.
First Author: Kirkpatrick
Date: 79,1,1
Author List: R.C. Kirkpatrick
Citation: Nuclear Fusion 19 (1), (1979)
Title: An overview of design space for small fusion targets
Abstract: A twelve-parameter burn code has been used to gain an overview of the design space available for laser and E-beam fusion targets. The results of a few thousand implosion calculations are presented here in terms of an initial-condition space. The initial conditions include temperature, density and pusher jump-off velocity. For marginal driving energy there is an isolated region in the initial-condition space (qo, ro) for which ignition may be achieved.
First Author: Lindemuth
Date: 95,7,11
Author List: I.R. Lindemuth, C.A. Ekdahl, C.M. Fowler, R.E. Reinovsky, S.M. Younger, V.K. Chernyshev, V.N. Mokhov, A.I. Pavlovskii
Citation: 10th IEEE Int. Pulsed Power Conference, Albuquerque, New Mexico, July 11-13, 1995, LA-UR-95-2868DE96000010, CONF-950750-40
Title: The Los Alamos/Arzamas-16 collaboration of ultrahigh magnetic fields and ultrahigh energy pulsed power
Abstract: The end of the Cold War has made possible some remarkable scientific adventures--joint research projects between scientific institutions of the United States and the Russian Federation. Perhaps most unprecedented of the new partnerships is a formal collaboration which has been established between the All-Russian Scientific Research Institute of Experimental Physics and the Los Alamos National Laboratory (LANL), the two institutes which designed the first nuclear weapons for their respective countries. In early 1992, emerging governmental policy in the US and Russia began to encourage ``lab-to-lab'' interactions between the nuclear weapons design laboratories of the two countries. Each government recognized that as nuclear weapons stockpiles and design activities were being reduced, highly qualified scientists were becoming available to use their considerable skills in fundamental scientific research of interest to both nations. VNIIEF and LANL quickly recognized a common interest in the technology and applications of magnetic flux compression, the technique for converting the chemical energy released by high-explosives into intense electrical pulses and intensely concentrated magnetic energy. This document reports on current projects of the collaboration.
First Author: Lindemuth
Date: 95,9,4
Author List: Lindemuth, I.R.; Yakubov, V.A.; Volkov, G.I.; Skobelev, A.N.; Seleznev, N.Y.; Pavlovskii, E.S.; Pak, S.V.; Morozov, I.V.; Mikhailov, O.D.; Korchagin, V.P.; etal.
Citation: Physical Review Letters 75 (10), 4 Sep. 1995, pp.1953-1956
Title: Target plasma formation for magnetic compression/magnetized target fusion
Abstract: Experimental observations of plasma behavior in a novel plasma formation chamber are reported. Experimental results are in reasonable agreement with two-dimensional magnetohydrodynamic computations suggesting that the plasma could subsequently be adiabatically compressed by a magnetically driven pusher to yield 1 GJ of fusion energy. An explosively driven helical flux compression generator mated with a unique closing switch/opening switch combination delivered a 2.7 MA, 347 ms magnetization current and an additional 5 MA, 2.5 ms electrical pulse to the chamber. A hot plasma was produced and 1013 D-T fusion reactions were observed.
First Author: Lindemuth
Date: 91,12,1
Author List: I.R. Lindemuth, R.C. Kirkpatrick
Citation: Fusion Technology 20, (Dec. 1991)
Title: The promise of magnetized fuel: high gain in inertial confinement fusion
Abstract: At the third International Conference on Emerging Nuclear Energy Systems, we presented computational results which suggested that ``breakeven'' experiments in inertial confinement fusion (ICF) may be possible with existing driver technology. Our computations used a simple zero-dimensional model to survey the parameter space available for magnetized fuel. The survey predicted the existence of a totally new region in parameter space where significant thermonuclear fuel burn-up can occur. The new region is quite remote from ``conventional'' parameter space and is characterized by very low fuel densities, very low implosion velocities, and, most importantly, driver requirements reduced by orders of magnitude. Whereas our initial computations considered only the yield from a hot, magnetized central fuel, we have extended our simple model to include a ``cold fuel'' layer. In the same spirit as our earlier work, our extended model is intended to provide a starting point for more comprehensive investigations. Our extended model predicts that it is possible to obtain a large cold fuel burn-up fraction, leading to very high gain, and once again, the optimum parameter space is quite remote from that of conventional high gain targets. Although conventional drivers optimized for conventional targets are probably not optimum for magnetized fuel at its extremes, there is a continuum between the conventional parameter space between the conventional parameter space and the new parameter space, suggesting a possible role for conventional drivers. However, it would appear that magnetized fuel warrants a complete rethinking of the entire driver/target configuration.
First Author: Lindemuth
Date: 83,6,1
Author List: I.R. Lindemuth, R.C. Kirkpatrick
Citation: Los Alamos National Laboratory preprint, LA-UR-82-3571, (1983)
Title: The Promise of magnetized fuel: inertial confinement fusion with existing driver technology
Abstract: A simple, zero-dimensional model describing the temporal behavior of an imploding-shell, magnetized-fuel inertial confinement fusion target is used to survey the parameter space available for magnetized fuel by computing the behavior of thousands of targets. The survey predicts the existence of a totally new region in parameter space where significant thermonuclear fuel burn-up can occur. The new region is characterized by very low fuel densities, very low implosion velocities, and most importantly, driver requirements reduced by several orders of magnitude, suggesting that 'break-even experiments may be possible with existing inertial confinement fusion drivers. The new parameter space for magnetized D-T fuel in both spherical and cylindrical geometries and for magnetized D-3 He fuel in spherical geometries is examined.
First Author: Lindemuth
Date: 83,1,1
Author List: I.R. Lindemuth, R.C. Kirkpatrick
Citation: Nuclear Fusion 23 (3), (1983)
Title: Parameter space for magnetized fuel targets in inertial confinement fusion
Abstract: A simple, zero-dimensional model describing the temporal behavior of an imploding-shell, magnetized fuel inertial confinement fusion target is formulated. The model includes effects not normally considered in inertial confinement fusion such as magnetic back-pressure on the imploding shell, magnetic reduction of thermal conductivity, magnetic diffusion, and Ohmic heating. The model is simple enough to permit a survey of the parameter space available for magnetized fuel by computing the behavior of thousands of targets. The survey predicts the existence of a totally new region in parameter space where significant thermonuclear fuel burn-up can occur. The new region is characterized by very low fuel densities, very low implosion velocities, and, most important, driver requirements reduced by several orders of magnitude, suggesting that 'break-even' experiments may be possible with existing inertial confinement fusion drivers. The computed results are in reasonable agreement with more complete two-dimensional magnetohydrodynamic simulations.
First Author: Lindemuth
Date: 81,4,1
Author List: I.R. Lindemuth, M.M. Widner
Citation: Phys. Fluids 24 (4), April 1981
Title: Magnetohydrodynamic behavior of thermonuclear fuel in a preconditioned electron beam imploded target
Abstract: Two-dimensional magnetohydrodynamic numerical calculations have been performed to study the fuel behavior of a preconditioned relativistic electron beam target in which, experimentally, a portion of the beam current prepulse entered the target to provide fuel preheat magnetothermoinsulation. The magnetohydrodynamic plasma model used includes radiation, thermal conduction, ionization, and resistive diffusion. The magnetohydrodynamic partial differen tial equations are solved by a computer code employing implicit finite-difference methods. The fuel is shown to develop counter-streaming vortices during the implosion phase. The computed neutron yield is in reasonable agreement with the experimental value, suggesting the origin of the neutrons to be thermonuclear. The effect of both magnetothermoinsulation and preheat is examined.
First Author: Lindemuth
Date: 78,10,1
Author List: I. R. Lindemuth, J.S. Pettibone, J.C. Stevens, R.C. Harding, D. M. Kraybill, L. J. Suter
Citation: Phys. Fluids 21 (10), October 1978
Title: Unstable behavior of hot, magnetized plasma in contact with a cold wall
Abstract: The behavior of a hot, magnetized plasma brought into contact with a cold wall is studied numerically in one and two dimensions. A fully nonlinear, time-dependent magnetohydrodynamic plasma model which includes thermal conduction, resistive diffusion, radiation, and ionization is used. The model is solved numerically with an Eulerian computer code which employs implicit finite difference methods. One-dimensional calculations for cylindrical geometry examine the effect of the electrical properties of the wall on the plasma. Two-dimensional calculations for cylindrical geometry show the formation of a wall-induced instability which enhances thermal conduction losses from the plasma; the reemergence of short wavelengths, a new feature of unstable behavior, is evident in the calculations. Two-dimensional calculations for toroidal geometry show that heat losses to a cold wall lead to double-vortex convection flow of the plasma with no evidence of the formation of smaller scale convective cells.
First Author: Lindemuth
Date: 78,1,1
Author List: I.R. Lindemuth, T.R. Jarboe
Citation: Nuclear Fusion 18 (7), (1978)
Title: Initial numerical studies of the behavior of z-pinch plasma under liner implosion conditions
Abstract: The principle of achieving thermonuclear temperatures by compression of a z-pinch plasma with a solid liner is demonstrated by one- and two-dimensional numerical calculations of the behaviour of the plasma under liner implosion conditions. The magnetohydrodynamic plasma model used includes radiation, thermal conduction, and resistive diffusion. The magnetohydrodynamic partial differential equations are solved by a computer code employing implicit finite-difference methods. The liner is represented by a moving, rigid wall, and the entire Eulerian finite-difference mesh linearly contracts as the liner moves inward. The effectsof end losses and unstable boundary layer formation are demonstrated. The plasma is shown to behave significantly nonadiabatically, although some plasma is nearly adiabatically compressed. For an assumed initial plasma/ magnetic-field configuration and an assumed liner velocity of 1 cm·ms-1, plasma of 10 cm-3 and 600 eV is heated to peak temperatures of nearly 20 keV when the plasma volume is reduced by a factor of 900.
First Author: Lindl
Date: 98,11,1
Author List: Lindl, J.
Citation: Phys. of Plasmas 2 (11) (United States), Nov. 1995, pp.3933-4024
Title: Development of the indirect-drive approach to inertial confinement fusion and the target physics basis for ignition and gain
Abstract: The ignition target requirements for hohlraum energetics, radiation symmetry, hydrodynamic instabilities and mix, laser plasma interaction, pulse shaping, and ignition requirements are all consistent with experiments. The NIF laser design, at 1.8 MJ and 500 TW, has the margin to cover uncertainties in the baseline ignition targets. In addition, data from the NIF will provide a solid database for ion-beam-driven hohlraums being considered for future energy applications. In this paper we analyze the requirements for indirect drive ICF and review the theoretical and experimental basis for these requirements. Although significant parts of the discussion apply to both direct and indirect drive, the principal focus is on indirect drive.
First Author: Logan
Date: 92,3,6
Author List: Logan, B.G.
Citation: American Nuclear Society annual meeting, 7-12 Jun 1992, Boston, MA (United States) UCRL-JC-109517; DE92011964 CONF-920606-16
Title: Low cost, high yield IFE reactors: revisiting Velikhov's vaporizing blankets
Abstract: The performance (efficiency and cost) of IFE reactors using MHD conversion is explored for target blanket shells of various materials vaporized and ionized by high fusion yields (5 to 500 GJ). A magnetized, prestressed reactor chamber concept is modeled together with previously developed models for the Compact Fusion Advanced Rankine II (CFARII) MHD Balance-of-Plant (BoP). Using conservative 1-D neutronics models, high fusion yields (20 to 80 GJ) are found necessary to heat Flibe, lithium, and lead-lithium blankets to MHD plasma temperatures, at initial solid thicknesses sufficient to capture most of the fusion yield. Advanced drivers/targets would need to be developed to achieve a ``Bang per Buck'' figure-of-merit approximately > 20 to 40 joules yield per driver $ for this scheme to be competitive with these blanket materials. Alternatively, more realistic neutronics models and better materials such as lithium hydride may lower the minimum required yields substantially. The very low CFARII BoP costs (contributing only 3 mills/kWehr to CoE) allows this type of reactor, given sufficient advances that non-driver costs dominate, to ultimately produce electricity at a much lower cost than any current nuclear plant.
First Author: Lovberg
Date: 94,1,1
Author List: R.H. Lovberg, R.A. Riley, J.S. Shlachter
Citation: Dense Z-Pinches, Third Int. Conf., M. Haines and A. Knight, Eds. (Am. Inst. Physics, NY, 1994), pp. 59-68
Title: Instability heating of the HDZP
Abstract: We present a model of dense Z-pinch heating. For pinches of sufficiently small diameter and high current, direct ion heating by m = 0 instabilities becomes the principal channel for power input. This process is particularly important in the present generation of dense micro-pinches (e.g. HDZP-II) where instability growth times are much smaller than current risetimes, and a typical pinch diameter is several orders smaller than that of the chamber. Under these conditions, m = 0 formation is not disruptive; the large Ez field reconnects the instability cusps externally, after which the ingested magnetic flux decays into turbulent kinetic energy of the plasma. The continuous process is analogous to boiling of a heated fluid.
First Author: McCullen
Date: 89,2,1
Author List: McCullen, J.D.; Neuman, W.A.; Morse, R.L.; Montierth, L.M.
Citation: Phys Fluids B 1 (2), Feb. 1989, pp.448-467
Title: Surface plasma structures in the kinetic regime
Abstract: A numerical study is done of a plasma in contact with a solid surface that reemits some fraction of the incident plasma as neutral gas. The calculation uses a steady-state, kinetic treatment of the transport equations in one space dimension and one or two velocity dimensions to determine self-consistently the distribution functions of the interacting species and the electrostatic potential. The dominant phenomena are the ionization of the neutral gas and the acceleration of the resulting ions away from a potential maximum that is predicted to form in the ionization region. Other effects involved are a Debye sheath structure between the solid surface and the potential maximum, and collisional trapping and untrapping of electrons in the well represented by the potential maximum. Results are presented from a nondimensional model with a monatomic returning neutral species, and for diatomic molecular deuterium returning from the surface. For each set of physical parameters chosen, a one parameter family of solutions is obtained. A hypothesis is presented for the choice from this family of solutions that would be found experimentally.
First Author: Meier
Date: 92,3,1
Author List: Meier, W.R.; Monsler, M.J.; Bieri, R.L.
Citation: DOE/ER/54100-1-Vol.1; DE93019139 WJSA-92-01-Vol.1
Title: Osiris and SOMBRERO inertial confinement fusion power plant designs vol. 1, executive summary and overview, final report
Abstract: Conceptual designs and assessments have been completed for two inertial fusion energy (IFE) electric power plants. The detailed designs and results of the assessment studies are presented in this report. Osiris is a heavy-ion-beam (HIB) driven power plant and SOMBRERO is a Krypton-Fluoride (KrF) laser-driven power plant. Both plants are sized for a net electric power of 1000 Mwe.
First Author: Moir
Date: 95,1,18
Author List: R. W. Moir.
Citation: Lawrence Livermore National Laboratory unpublished presentation, Fusion Skunk Works, January 18, 1995.
Title: PACER Revisited: History and Future Challenges
Abstract: (none)
First Author: Montierth
Date: 92,4,1
Author List: Montierth, L.M.; Morse, R.L.; Neuman, W.A.
Citation: Phys. of Fluids B 4 (4) (United States), Apr. 1992, pp.784-795
Title: Fluid model treatment of surface plasma structures
Abstract: A fluid model is presented for the purpose of calculating numerically the structures of surface plasmas with neutrals returning from the surface, in collision-dominated parameter regimes. Limiting corrections to thermal conduction and viscous pressure are obtained through comparisons with previous Fokker--Planck transport calculations. The model includes removal by pumping, as well as by ionization, of some of the returning neutrals, and solutions are obtained for different relative strengths of pumping. Increasing velocities of plasma flow toward the surface and increasing plasma temperatures near the surface are seen with increased pumping. In the asymptotic region, far from the surface, agreement is found between these families of numerical model solutions and two classes of analytic solutions. Applications to other fundamental and applied problems are discussed.
First Author: Montierth
Date: 89,9,1
Author List: Montierth, L.M.; Neuman, W.A.; Morse, R.L.
Citation: Phys Fluids B 1 (9), Sep. 1989, pp.1911-1925
Title: Collisional transport treatment of surface plasma structures
Abstract: Calculations are shown of the structure of plasmas in equilibrium with solid surfaces that reemit incident plasma ions as relatively cold neutral gas. A numerical transport model that includes a Fokker--Planck treatment of ion--ion collisions obtains the distribution function for ions in a phase space of one spatial coordinate and two velocities. This is done self-consistently with an electrostatic potential, a Maxwell--Boltzmann description of electrons, and electron impact ionization of the reemited neutrals. Solutions are obtained from a higher temperature kinetic regime where Coulomb collisions are nearly negligible to a lower temperature regime where plasma behavior is approximately fluidlike. A result of these calculations is the resolution of an ambiguity posed by previous kinetic regime calculations that omitted ion--ion collisions and obtained a family of solutions for each set of physical parameters [Phys. Rev. Lett. 49, 650 (1982); Phys. Fluids 1, 448 (1989)]. The physically correct solution for semi-infinite surface plasmas is shown to be the member of each family that maximizes the ion thermal conduction to the surface and the magnitude of a maximum in the electrostatic potential that is found in these and the previous calculations. Further results are in agreement at lower temperatures with solutions obtained from a fluid model and the identification of the correct boundary condition on normal flow velocity to be used in fluid models.
First Author: Moses
Date: 79,12,1
Author List: R.W. Moses, R.A. Krakowski, R.L. Miller
Citation: Los Alamos Scientific Laboratory informal report, LA-7686-MS (1979)
Title: A conceptual design of the fast-liner reactor (FLR) for fusion power
Abstract: The generation of fusion power from the Fast-Liner Reactor (FLR) concept envisages the implosion of a thin (3-mm) metallic cylinder (0.2-m radius by 0.2-m length) onto a preinjected plasma. This plasma would be heated to thermonuclear temperatures by adiabatic compression, pressure confinement would be provided by the liner inertia, and thermal insulation of the wall-confined plasma would be established by an embedded azimuthal magnetic field. A 2- to 3-ms burn would follow the ~104 m/s radial implosion and would result in a thermonuclear yield equal to 10-15 times the energy initially invested into the liner kinetic energy. For implosions occurring once every 10 s a gross thermal power of 430 MWt would be generated. The results of a comprehensive systems study of both physics and technology (economics) optima are presented. Despite unresolved problems associated with both the physics and technology of the FLR, a conceptual power plant design is presented.
First Author: Olsen
Date: 79,5,1
Author List: J.N. Olsen, M.M. Widner, J. Chang, L. Baker
Citation: J. Appl. Phys. 50 (5), May 1979
Title: Fuel preconditioning studies for e-beam fusion targets
Abstract: Fuel temperature and density conditions, achieved during the preheat phase of electron-beam fusion compression experiments, must be accurately known to understand experimental results via numerical simulations. We present studies of discharge preheating in a simplified cylindrical geometry which compare measured quantities with results from the one-dimensional Lagrangian CHARTB magnetohydrodynamic code. Experimental meaurements included schlieren photography and ultraviolet through visible time- and space- resolved spectroscopy in various configurations. It is seen that an 8-kA 500-ns heating pulse in 100 Torr of D2+10% O2 produces 10--12 eV temperatures, 1018 cm-3 electron densities, and 7 x 105 cm/s expansion velocities in the heated discharge channel. These results are consistent with previous claims for neutron-producing targets, although the target geometry is different.
First Author: Parker
Date: 93,11,1
Author List: J. Parker
Citation: Los Alamos National Laboratory ATHENA Technical Report No. 1 (November 1993).
Title: A primer on liner implosions with particular application to the Pegasus II capacitor bank
Abstract: (none)
First Author: Sheehey
Date: 97,1,1
Author List: P. Sheehey, I. Lindemuth
Citation: Phys. Plas. 4 (1), (1997)
Title: Hall and two-temperature magnetohydrodynamic simulation of deuterium-fiber-initiated z pinches
Abstract: Two-dimensional "cold-start" resistive magnetohydrodynamic computations of formation and evolution of deuterium-fiber-initiated Z pinches have been extended to include separate ion and electron energy equations and some finite-Lamor-radius ordered terms. In the Ohms law (magnetic field evolution) equation, Hall and diamagnetic pressure terms have been added, and corresponding terms have been added to the energy equation. None of the extended model computations show stabilizing effects for fiber-initiated Z pinches; in fact, further slight destabilization is noted. This continues the good agreement shown between previous computational results and experiment.
First Author: Sheehey
Date: 96,1,1
Author List: P. Sheehey, J. Guzik, R. Kirkpatrick, I. Lindemuth, D. Scudder, J. Shlachter, F. Wysocki
Citation: Fusion Technology 30, 1355 (1996)
Title: Computational and experimental investigation of magnetized target fusion
Abstract: In Magnetized Target Fusion (MTF), a preheated and magnetized target plasma is hydrodynamically compressed to fusion conditions. Because the magnetic field suppresses losses by electron thermal conduction in the fuel during the target implosion heating process, the compression may be over a much longer time scale than in traditional inertial confinement fusion (ICF). Bigger targets and much lower initial target densities than in ICF can be used, reducing radiative energy losses. Therefore, 'liner-on-plasma' compressions, driven by relatively inexpensive electrical pulsed power, may be practical. Potential MTF target plasmas must meet minimum temperature, density, and magnetic field starting conditions, and must remain relatively free of high-Z radiation-cooling-enhancing contaminants. At Los Alamos National Laboratory, computational and experimental research is being pursued into MTF target plasmas, such as deuterium-fiber-initiated Z-pinches, and the Russian-originated 'MAGO' plasma. In addition, liner-on-plasma compressions of such target plasmas to fusion conditions are being computationally modeled, and experimental investigation of such heavy liner implosions has begun. The status of the research will be presented. 9 refs., 4 figs.
First Author: Sherwood
Date: 81,1,1
Author List: A.R. Sherwood, F.L. Ribe
Citation: Fusion 1, Part B (Academic Press, 1981), E. Teller, Ed., p. 59
Title: Fast-liner-compression fusion systems
Abstract: Fast-liner-compression systems are essentially inertial confinement systems which use magnetic fields to insulate the plasma and to drive the compressing liner. The plasma is in contact with the imploding metallic liner wall and has an internal magnetic field. With respect to this magnetic field, the plasma beta is much greater than unity. At its ends the plasma is in contact with material end plugs, whose ablating surfaces confine the fusion plasma in the axial direction.
First Author: Sherwood
Date: 77,8,1
Author List: A.R. Sherwood, B.L. Freeman, R.A. Gerwin, T.R. Jarboe, R.A. Krakowski, R.C. Malone, J. Marshall, R.L. Miller, B. Suydam
Citation: Los Alamos Scientific Laboratory proposal, LA-6707-P, (1977)
Title: Fast liner proposal
Abstract: This is a proposal to study, both theoretically and experimentally, the possibility of making a fusion reactor by magnetically imploding a cylindrical metallic shell on a prepared plasma. The approach is characterized by the following features: (1) the nonrotating liner would be driven by an axial current, (2) the plasma would also carry an axial current that provides an azimuthal magnetic field for thermal insulation in both the radial and longitudinal directions, (3) solid end plugs would be utilized to prevent axial loss of particles, and (4) liner speeds would be in the 106 cm/s range.
Our preliminary calculations indicate (1) that the energetics are favorable (energy inputs of about 10 MJ might produce a machine in the break-even regime), (2) that radiation and heat losses could be made tolerable, (3) that alpha-particle heating could be made very effective, and (4) that Taylor instabilities in a fast liner might be harmless because of the large viscosities at high pressures.
A preliminary conceptual design of the sort of fusion reactor that might result from such an approach is discussed, as are some of the relevant reactor scaling arguments.
First Author: Siemon
Date: 97,3,5
Author List: R. E. Siemon
Citation: Los Alamos National Laboratory talk LA-UR-97-764, presented at the Innovative Confinement Concept Workshop, Marina del Rey, California, March 3-6, 1997.
Title: Magnetized target fusion - a high-density pulsed-power approach to fusion
Abstract: Magnetized Target Fusion (MTF) is a new thrust in fusion energy research that would utilize plasma parameters intermediate (n = 1018 to 1020 cm-3) between inertial confinement fusion (n ~ 1024 cm-3) and conventional magnetic fusion (n ~ 1014cm-3). The idea is to compress a magnetized plasma inside an electrically conducting shell imploded at hypervelocity. Pulsed power technology developed under the auspices of Defense Programs is capable of generating peak-pressure dwell-time products of relevance to fusion (ntT). Magnetic field in the compressed plasma is needed to suppress thermal conduction in the regime of interest (liner velocity of a few cm per microsecond). Plasma beta greater than unity with pressure supported by material walls is desirable. Examples of radial density and temperature profile evolution in a preheated cylindrical z pinch and theta pinch have been calculated using Braginskii transport coefficients. The results show parameters fairly close to simple adiabatic heating expectations for realistic liner compression speeds even though a significant amount of plasma accumulates in a cold low-beta sheath at the metal boundary. A bibliography of relevant papers on the physics of MTF is being assembled and is available on the web at http://wsx.lnl.gov/mtf_bib.html. As a pulsed system with explosive energy densities, MTF is akin to ICF as a future energy technology. A possible key advantage for long-term energy development is that MTF appears to require less capital investment than other approaches, and thus has the potential for a significantly lower-cost development program. The first phase of needed research will advance the science of wall-plasma interactions, which may impact our understanding of tokamak disruptions or have application to plasma processing. An exciting possibility is that after successful work on plasma preheating, MTF could provide a modest-cost approach to studying alpha physics and thermonuclear burn phenomena.
First Author: Siemon
Date: 86,6,7
Author List: R. E. Siemon, W. T. Armstrong, D. C. Barnes, R. R. Bartsch, R. E. Chrien, J. C. Cochrane, W. N. Hugrass, R. W. Kewish, Jr., P. L. Klingner, H. R. Lewis, R. K. Linford, K. F. McKenna, R. D. Milroy, D. J. Rej, J. L. Schwarzmeier, C. E. Seyler, E. G. Sherwood, R. L. Spencer, M. Tuszewski
Citation: Fusion Technology 9(1), 13-37 (January 1986).
Title: Review of the Los Alamos FRX-C experiment
Abstract: The FRX-C device is a large field-reversed theta pinch experiment with linear dimensions twice those of its FRX-A and FRX-B predecessors. It is used to form field-reversed configurations (FRCs), which are high-beta, highly prolate compact toroids. The FRX-C has demonstrated an R2 scaling for particle confinement in FRCs, indicating particles are lost by diffusive processes. Particle losses were also observed to dominate the energy balance. When weak quadrupole fields were applied to stabilize the n = 2 rotational mode, FRC lifetimes >300 ms were observed. Detailed studies of the FRC equilibrium were performed using multichord and holographic interferometry. Measurements of electron temperature by Thomson scattering showed a flat profile and substantial losses through the electron channel. The loss rate of the internal poloidal flux of the FRC was observed to be anomalous and to scale less strongly with temperature than predicted from classical resistivity.
First Author: Siemon
Date: 80,12,2
Author List: R. E. Siemon, R. R. Bartsch
Citation: Proc. 3rd Symp. Physics and Technology of Compact Toroids, Los Alamos, New Mexico, December 2-4, 1980, LA-8700-C, p. 172, Los Alamos National Laboratory (1980)
Title: Scaling laws for FRC formation and prediction of FRX-C parameters
Abstract: A semi-emperical method has been developed to extrapolate the experimental results from FRX-B, a field-reversed theta pinch which generates an FRC (Field-Reversed Configuration - a compact toroid with no toroidal field), to the larger size FRX-C. Even though there are many uncertainties about details the dynamic processes by which an FRC is formed, the scaling exercise has proven useful in identifying limitations in the original FRX-C design and the design has been modified to have a lower voltage and larger capacitance. The goal of FRX-C remains unchanged: to test the confinement scaning of an FRC in a larger device over a wider range of temperatures. Of particular interest is the testing of possible MHD stability limits as the ratio of plasma size to gyro radius increases.
First Author: Smitherman
Date: 91,12,1
Author List: D.P.Smitherman, R.C. Kirkpatrick
Citation: Fusion Technology 20 (Dec. 1991)
Title: Energetic alpha particle deposition in a magnetized plasma
Abstract: The problem of energetic alpha particle deposition in a dense, magnetized deuterium-tritium (DT) thermonuclear fuel has been studied numerically for the case of coulomb interactions in cylindrical geometry. This was done by following the particle trajectories initiated at various radii and in different directions through the plasma and its imposed field until they had either left the plasma or deposited all their energy. The resulting complex particle trajectories in the static magnetized fuel make a detailed treatment of the problem computationally intensive. Therefore, we have attempted to use detailed modeling to produce a data base for a neural nets algorithm for incorporation in an ignition critical profile code. While the accuracy of the neural net in reproducing the detailed calculational results is not high, it is approximately 6000 times faster.
First Author: Sweeney
Date: 81,1,1
Author List: M.A. Sweeney, A.V. Farnsworth, Jr.
Citation: Nuclear Fusion 21 (1), (1981)
Title: High-gain, low-intensity ICF targets for a charged-particle beam fusion driver
Abstract: A class of high-gain ICF targets driven by electrons or light ions is discussed. The targets are characterized by low-beam-intensity requirement and large size. A magnetic field provides thermal insulation of pre-heated, low-density fuel. The addition of a cryogenic fuel layer increases the gain without requiring significantly increased beam power and intensity. The higher fuel adiabat and reduced fuel losses produce ignition and burn for lower implosion velocities and at lower power and intensity than conventional ablative designs. Gains of 20 to 40 are expected for intensities of approximately < 80 TW·cm-2, initial magnetic fields of approximately > 30-60 kG, an initial fuel radius of 0.2-0.4 cm, and irradiation uniformities of 6-7%. Driver requirements are approximately <45 TW·cm-2 if the initial magnetic field is approximately >300-600 kG, sufficient for alpha trapping in the compressed low-density fuel. Voltage shaping increases fuel burn-up and target rr and lowers power and intensity levels by an additional factor of about 0.6.
First Author: Tabak
Date: 94,5,1
Author List: Tabak, M.; Mason, R.J.; Perry, M.D.; Campbell, E.M.; Woodworth, J.; Wilks, S.C.; Kruer, W.L.; Glinsky, M.E.; Hammer, J.
Citation: Physics of Plasmas 1 (5) (United States), May 1994, pp.1626-1634
Title: Ignition and high gain with ultra-powerful lasers
Abstract: Ultrahigh intensity lasers can potentially be used in conjunction with conventional fusion lasers to ignite inertial confinement fusion (ICF) capsules with a total energy of a few tens of kilojoules of laser light, and can possibly lead to high gain with as little as 100 kJ. A scheme is proposed with three phases. First, a capsule is imploded as in the conventional approach to inertial fusion to assemble a high-density fuel configuration. Second, a hole is bored through the capsule corona composed of ablated material, as the critical density is pushed close to the high-density core of the capsule by the ponderomotive force associated with high-intensity laser light. Finally, the fuel is ignited by suprathermal electrons, produced in the high-intensity laser--plasma interactions, which then propagate from critical density to this high-density core. This new scheme also drastically reduces the difficulty of the implosion, and thereby allows lower quality fabrication and less stringent beam quality and symmetry requirements from the implosion driver. The difficulty of the fusion scheme is transferred to the technological difficulty of producing the ultrahigh-intensity laser and of transporting this energy to the fuel.
First Author: Tidman
Date: 82,1,1
Author List: D.A. Tidman, S. A. Goldstein
Citation: IEEE Transactions on Magnetics 18 (1), January 1982
Title: Applications of REP-ratable mass accelerators (such as MAID)
Abstract: Several applications of mass-accelerators are discussed with emphasis on impact fusion as one of the most ambitious goals for such devices. Many applications require that the accelerator be capable of being repetitively fired. 20 refs.
First Author: Tuszewski
Date: 91,5,24
Author List: M. Tuszewski, D. P. Taggart, R. E. Chrien, D. J. Rej, R. E. Siemon, B. L. Wright
Citation: Phys. Fluids B 3(10), 2856-2870 (October 1991)
Title: Axial dynamics in field-reversed theta pinches. II: stability
Abstract: Detailed stability studies are made with new diagnostics in the FRX-C/LSM field-reversed theta pinch [Plasma Physics and Controlled Nuclear Fusion Research (IAEA, Vienna, 1989), Vol II, p. 517]. These studies seek the origin of a degradation of the confinement properties of field-reversed configurations (FRCs) that appears associated with strong axial dynamics during plasma formation. Several instabilities are observed, including rotational modes, interchanges, and tilt instabilities. Only the latter are strongly correlated with FRC confinement. Title instabilities are observed for FRCs with larger average number of ion gyroradii (s ~ 3-5) and smaller separatrix elongations (e ~ 3-4). Coincidently, strong axial dynamics occurs for cases with larger s and smaller e values, through increases in either reversed bias field or fill pressure. These data provide some understanding of FRC stability. In agreement with finite Larmor radius theory, there is a regime of gross stability for the very kinetic and elongated FRCs with s/e < 0.2-0.3. This is the regime that has been studied in most FRC experiments. However, tilt and other instabilities are observed for FRCs with s/e ~ 1. Additional stabilization techniques will be required for future large-size FRCs.
First Author: Tuszewski
Date: 88,11,1
Author List: M. Tuszewski
Citation: Nuclear Fusion 28(11), 2033-2092 (1988)
Title: Field reversed configurations
Abstract: The review is devoted to field reversed configurations and to the related field reversed mirrors; both are compact toroids with little or no toroidal magnetic field. Experimental and theoretical results on the formation, equilibrium, stability and confinement properties of these plasmas are presented. Although they have been known for about three decades, field reversed configurations have been studied intensively only in years. This renewed interest is due to the unusual fusion reactor potential of these high beta plasmas and also to their surprising macroscopic stability. At the present time, field reversed configurations appear to be completely free of gross instabilities and show relatively good confinement. The primary research goal for the near future is to retain these favourable properties in a less kinetic regime. Other important issues include the development of techniques for slow formation and stability, and a clearer assessment of the confinement scaling laws. (author). 416 refs, 37 figs, 8 tabs.
First Author: Vekshtein
Date: 90,1,1
Author List: G.E. Vekshtein
Citation: Rev. Plas. Physics 15 (Consultants Bureau, NY, 1990)
Title:
Abstract:
First Author: Vekshtein
Date: 75,1,1
Author List: Vekshtein, G.E.; Chebotaev, P.Z.; Ryutov, D.D.
Citation: Sov. J. Plasma Phys.1 (3) (Engl. Transl.), (1975), pp.220-222
Title: Diffusion of heavy impurities in a dense, wall-confined plasma
Abstract: The theoretical analysis considers a single species of impurity ions with a specified charge. The mass of these ions is assumed to be much larger than the mass of the heavy ions. Radial profiles of the plasma velocity, density, and temperature for the case of heating by a high-power relativistic beam are given. Impurity effects are shown.
First Author: Winterberg
Date: 81,1,1
Author List: F. Winterberg
Citation: Atomkernenergie/Kerneichnik Bd. 38 (1981) Lfg. 2
Title: Magnetic booster target inertial confinement fusion driver
Abstract: Results are presented for the new driver concept for inertial confinement fusion recently proposed. In this new concept a first or booster stage is a magnetized relatively low density DT target driven by an initial high energy but relatively low power source. The thermonuclear energy released in the first stage low density magnetized DT target, after being converted into black body radiation, is then used to drive a second stage high density target by ablative implosion, resulting in the release of large quantities of thermonuclear energy. The proposed novel concept has the potential of a near-term low-cost driver for an inertial confinement fusion reactor.