RSICC CODE PACKAGE CCC-746
1. NAME AND TITLE
MCNPX 2.6.0: Monte Carlo All‑Particle Transport Code System and MCNPDATA.
RELATED DATA LIBRARIES included in the distribution
MCNPDATA: Standard Neutron, Photoatomic, Photonuclear, and Electron Data Libraries for MCNP and MCNPX from the November 2005 data release for MCNP Version 5.1.40 / MCNPX 2.5.0 in RSICC package CCC-730. Release of new MCNPDATA libraries derived from ENDF/B-VII have encountered a slight delay and will be released later with MCNP5 1.50 and a re-release of this MCNPX 2.6.0 package. No patches will be released to create new versions of the codes from the current release, and no free upgrades will be distributed.
AUXILIARY PROGRAMS included in the distribution
GRIDCONV: Converts output of mesh and radiography tallies to input for external graphics programs.
HTAPE3X: Postprocessor for MCNPX HISTP output.
MAKXSF: Prepares MCNPX Cross‑Section Libraries.
HCNV and TRX: Convert LAHET ASCII data to binary.
XSEX3: Analyzes a HISTP history file and generates double‑differential particle production cross sections for primary beam interactions
VISED X_22S: Visual Editor for interactively constructing & visualizing MCNPX geometry (runs on Windows PCs only). More VISED information is on the web at the Visual Consultants website http://www.mcnpvised.com/.
See the information file for data libraries later in this file. Documentation on the data libraries may be found in Appendix G of the MCNPX manual and on the web http://www-xdiv.lanl.gov/projects/data/nuclear/mcnpdata.html.
Some additional libraries developed for MCNPX are also distributed. Libraries specific to the LAHET Bertini model are included in a binary file called BERTIN. Gamma de-excitation probabilities and energy lines are included in a binary file called PHTLIB. High-energy total, reaction and elastic cross sections are contained in an ASCII file called BARPOL.DAT. The photonuclear model physics, provided through the CEM physics package, utilizes the resonance data provided in the ASCII file GDR.DAT. The CEM and LAQGSM event generators also use several other ASCII files (ATAB.DAT, CHANNEL1.TAB, GAMMAN.TBL, LEVEL.TBL, MASS.TBL, SHELL.TBL). Several ASCII files are provided for the INCL physics package (FLALPHA.TAB, FRLDM.TAB, VGSLD.TAB, PACE2.DATA). The CINDER90 transmutation code currently uses two ASCII databases (CINDER.DAT, CINDERGL.DAT).
MCNPX includes a test library of cross sections for running sample problems, but this test library is not suitable for real problems. Running the code requires continuous energy cross-section data included with the MCNPX distribution. This library distribution includes the standard MCNP libraries, along with the LA150H proton data tables for 41 isotopes and the ASCII data files mentioned above. It should be noted that only the LA150 libraries (LA150N, LA150U, LA150H) contain emission data for light ions (i.e., Z=1-2), and in many cases only above 20 MeV (details are provided in the MCNPX User’s Manual).
2. CONTRIBUTOR
Los Alamos National Laboratory, Los Alamos, New Mexico.
3. CODING LANGUAGE AND COMPUTER
Fortran 90 and C; Windows PCs, Linux PCs, Sun; IBM; DEC (C00746MNYCP00).
4. NATURE OF PROBLEM SOLVED
MCNPX (MCNP eXtended) is a Fortran90 (F90) Monte Carlo radiation transport computer code that transports many particles over a broad range of energies. It is a superset of MCNP4C3 and has many capabilities beyond MCNP4C3. MCNPX is a production computer code that models the interaction of radiation with matter. New capabilities and enhancements of MCNPX 2.6.0 beyond MCNPX 2.5.0 are listed below. For details, see LA-UR-08-1808.pdf posted on the MCNPX website http://mcnpx.lanl.gov/.
• Depletion/burnup;
• Heavy-ion (Z>2) transport;
• LAQGSM physics model;
• CEM03 physics;
• Long file names;
• Delayed-particle emission;
• Criticality source convergence acceleration;
• Energy-time weight windows;
• Spherical mesh weight windows;
• Charged ions from neutron capture in table range;
• Tallies terminated at desired precision: STOP card;
• Numerous corrections/enhancements/extensions;
• Muon capture physics.
MCNPXTM is a general purpose Monte Carlo radiation transport code that tracks nearly all particles at nearly all energies. The official release date of MCNPX 2.6.0 is April 30, 2008. MCNPX began in 1994 as a code-merger project of MCNP 4B and LAHET 2.8. It was first released to the public in 1999 as version 2.1.5. In 2002, MCNPX was upgraded to MCNP 4C, converted to Fortran 90, enhanced with 12 new features, and released to the public as version 2.4.0. The release of version 2.6.0 includes many new features described in the “MCNPX Extensions Version 2.6.0” document which is provided with the MCNPX distribution. The depletion/burnup capability is based on CINDER90 and MonteBurns. MCNPX depletion is a linked process involving steady-state flux calculations in MCNPX and nuclide depletion calculations in CINDER90. Currently, the depletion/burnup/transmutation capability is limited to criticality (KCODE) problems. Physics improvements include a new version of the Cascade-Exciton Model (CEM), the addition of the Los Alamos Quark-Gluon String Model (LAQGSM) event generator, and a substantial upgrade to muon physics. Current physics modules include the Bertini and ISABEL models taken from the LAHET Code System (LCS), CEM 03, and INCL4. Many new tally source and variance-reduction options have been developed. MCNPX is released with libraries for neutrons, photons, electrons, protons and photonuclear interactions. In addition, variance reduction schemes (such as secondary particle biasing), and new tallies have been created specific to the intermediate and high energy physics ranges. The ‘mesh’ and ‘radiography’ tallies were included for 2 and 3‑dimensional imaging purposes. Energy deposition received a substantial reworking based on the demands of charged‑particle high‑energy physics. An auxiliary program, GRIDCONV, converts the mesh and radiography tally as well as standard MCTAL-file results for viewing by independent graphics packages. The code may be run in parallel at all energies via PVM or MPI. Information about MCNPX development can be found on the web site http://mcnpx.lanl.gov/.
5. METHOD OF SOLUTION
All capabilities of MCNP4C3 have been retained. Consult the MCNPX User’s Manual for applicability to high energy applications.
6. RESTRICTIONS OR LIMITATIONS
All standard MCNP neutron libraries over their stated ranges (~0-20 MeV).
Neutrons in the LA150 library from 0.0 - 150.0 MeV in tabular range for 42 isotopes
(except for 9Be to 100 MeV).
Neutrons from 1.0 MeV in the physics model regime.
Photons from 1 keV - 100 GeV.
Photonuclear interactions from 1.0 to 150.0 MeV in tabular range for 12 isotopes.
Photonuclear interactions from 1.0 MeV in the CEM physics model.
Electrons from 1 keV - 1 GeV.
Protons from 1.0 to 150.0 MeV in tabular range for 41 isotopes.
Protons from 1.0 MeV in the physics model regime.
Pions, muons, and kaons are treated only by physics models.
Light ions from 1 MeV/nucleon in the physics model regime.
Heavy ions from 3 MeV/nucleon in the LAQGSM physics model.
7. TYPICAL RUNNING TIME
Runtimes vary depending on computer speed and problem parameters. On a 2 GHz Pentium 4, compilation of MCNPX takes about 5 minutes. Test cases run in about 5 minutes.
8. COMPUTER HARDWARE REQUIREMENTS
MCNPX runs under Unix, Linux, and Windows operating systems and has been implemented on various 32-bit and 64-bit workstations and personal computers. The compiled version of the code tends to run ~8 Mbytes. Dynamic allocation makes memory demands variable on all platforms.
9. COMPUTER SOFTWARE REQUIREMENTS
C and Fortran 90 compilers are required to compile. The GNU make utility is required to build the system on Unix and Linux platforms. The GNU make.exe utility is included for Windows users. The only graphics support for this release is X11 http://www.x.org/. This is a Fortran 90 version of MCNPX which uses standard F90 allocation schemes for dynamic variables on all platforms. The package includes MCNPX 2.6.0 executables created by the LANL developers for the systems listed below. Each of these files contains precompiled executables and corresponding binary data libraries for bertin and phtlib.
Win32.zip: Windows executables, with Intel 9.1 on a 32-bit XP OS.
Win32I8.zip: Windows 8-byte integer executables, with Intel 9.1 on a 32-bit XP OS.
Win32MPI.zip: Windows MPICH-2 executables, with Intel 9.1 on a 32-bit XP OS.
Win32MPII8.zip: Windows 8-byte integer MPICH-2 executables, with Intel 9.1 on a 32-bit XP OS.
Win32CVF.zip: Windows executables, with CVF 6.6 on a 32-bit XP OS.
Linux.tar.gz: Linux executables, with INTEL 9.1 on a 64-bit GNU/Linux OS.
SUN.tar.gz: Sun executables, with XXX on a 32-bit Solaris OS.
RSICC tested this release on the following systems:
Intel Pentium running RedHat Enterprise Linux 4 with Intel 9.1.
Pentium 4 running Windows with Intel 9.1
DEC6600 running Tru64 Unix V5.1A with HP Fortran V5.5A and C V6.4.
10. REFERENCES
a) included in documentation
D. B. Pelowitz, ed., “MCNPX User's Manual, Version 2.6.0,” LA-CP-07-1473 (April 2008).
J. S. Hendricks et al., “MCNPX 2.6.0 Extensions,” LA-UR-08-2216 (April 2008).
A.L. Schwarz , R.A. Schwarz, and L.L. Carter, “MCNP/MCNPX Visual Editor Computer Code Manual For Vised Version 22S,” (February, 2008).
Documentation on the MCNPDATA libraries may be found in Appendix G of the MCNPX manual and on the web http://www-xdiv.lanl.gov/projects/data/nuclear/mcnpdata.html
b) background references:
D. B. Pelowitz, ed., “MCNPX User's Manual, Version 2.5.0,” LA-CP-05-0369 (April 2005).
L. S. Waters, Ed., “MCNPX User’s Manual, Version 2.4.0,” LA-CP-02-408 (Sept. 2002).
L. S. Waters, Ed., “MCNPX User’s Manual, Version 2.3.0,” LA-UR-02-2607 (April 2002).
J. F. Briesmeister, Ed., “MCNP ‑ A General Monte Carlo N‑Particle Transport Code, Version 4C,” LA‑13709‑M (April 2000).
R. E. Prael and H.Lichtenstein, “User Guide to LCS: The LAHET Code System,” LA‑UR‑89‑3014, Revised (September 15, 1989).
M. B. Chadwick, P. G. Young, S. Chiba, S. C. Frankle, G. M. Hale, H. G. Hughes, A. J. Koning, R. C. Little, R. E. MacFarlane, R. E. Prael, and L. S. Waters, “Cross Section Evaluations to 150 MeV for Accelerator‑Driven Systems and Implementation in MCNPX,” Nuclear Science and Engineering 131, Number 3 (March 1999) 293.
M. B. Chadwick, P. G. Young, R. E. MacFarlane, P. Moller, G. M. Hale, R. C. Little, A. J. Koning and S. Chiba, “LA150 Documentation of Cross Sections, Heating, and Damage: Part A (Incident Neutrons) and Part B (Incident Protons),” LA‑UR‑99‑1222 (1999).
S. G. Mashnik, A. J. Sierk, O. Bersillon, and T. A. Gabriel, “Cascade‑Exciton Model Detailed Analysis of Proton Spallation at Energies from 10 MeV to 5 GeV,” Nucl. Instr. Meth. A414 (1998) 68. (Los Alamos National Laboratory Report LA‑UR‑97‑2905).
Stepan G. Mashnik, Konstantin K. Gudima, Arnold J. Sierk, Mircea I. Baznat, and Nikolai V. Mokhov, “CEM03.01 User Manual,” Los Alamos National Laboratory report LA-UR-05-7321 (2005); RSICC Code Package PSR-532, http://www-rsicc.ornl.gov/codes/psr/psr5/psr-532.html/ (2006).
S. G. Mashnik, K. K. Gudima, M. I. Baznat, A. J. Sierk, R. E. Prael, and N. V. Mokhov, “CEM03.S1, CEM03.G1, LAQGSM03.S1, and LAQGSM03.G1 Versions of CEM03.01 and LAQGSM03.01 Event-Generators,” Los Alamos National Laboratory report LA-UR-06-1764 (March 6, 2006), also available at http://mcnpx.lanl.gov > documents.
W. B. Wilson et al., “Recent Development of the CINDER'90 Transmutation Code and Data Library for Actinide Transmutation Studies," Proc. GLOBAL'95 Int. Conf. on Evaluation of Emerging Nuclear FuelCycle Systems, Versailles, France, p. 848, September 11–14 (1995).
11. CONTENTS OF CODE PACKAGE
MCNPX code and data files are distributed on a single DVD in GNU compressed Unix tar files. WinZIP 8.0 is required to expand mcnpx files under Windows. The package includes MCNPX source code, MCNPDATA, VISED executable for Windows, makefiles, build scripts, executables for PC Windows, PC Linux, and Sun/Solaris; test problems, and the referenced electronic documents listed in Section 10.a above. An optional Windows installer is included to install MCNPDATA. The installer uses the open-source 7z.exe program to expand the files under Windows then sets environmental variable DATAPATH.
12. DATE OF ABSTRACT
May 2008.
KEYWORDS: CHARGED PARTICLES; COMPLEX GEOMETRY; ELECTRON; GAMMA‑RAY; HIGH ENERGY; KAON; MONTE CARLO; NEUTRON; PION; PROTON; RADIOGRAPHY; SPALLATION; RADIATION TRANSPORT
RSICC CODE PACKAGE CCC-746
Package NAME AND TITLE:
MCNPX 2.6.0: Monte Carlo All‑Particle Transport Code System and MCNPDATA.
File readme_data.txt:
Version: Nov 2005 Data Release for MCNP Version 5.1.40 / MCNPX 2.5.0
LANL No.: LA-CC-02-083, LA-CC-02-057
Files: MCNP DATA:
100xs 531dos 532dos actia actib dre5 drmccs
el el03 endf5mt endf5p endf5u endf60 endf62mt
endf66a endf66b endf66c endf66d endf66e endf6dn endl92
kidman la150h la150n la150u llldos mcplib mcplib02
mcplib03 mcplib04 mgxsnp misc5xs newxs newxsd rmccs
rmccsa sab2002 specs t16_2003 therxs tmccs uresa
xsdir
Date: 2005-11-01
Contacts: Bob Little
MCNP DATA Team Leader, X-Division, LANL
rcl@lanl.gov
MCNP DATA: Standard Neutron, Photoatomic, Photonuclear, and Electron Data
Libraries for MCNP and MCNPX.
These cross-section libraries are released by the Data Team in X-Division at Los Alamos National Laboratory for use with the MCNP Monte Carlo code package. This release includes all of the X-Division distributed neutron data libraries, the photoatomic libraries, photonuclear data library LA150U, the electron libraries EL1 and EL03, an updated XSDIR file, and a SPECS file for use with MAKXSF to convert the ascii data libraries into binary form. This release is intended to completely replace previous RSICC releases DLC-105, DLC-181, DLC-189, DLC-200, DLC-205 as well as the cross sections previously included with CCC-200/MCNP4A and CCC-710/MCNP5 1.30. The release will be updated as new libraries become available.
This README file provides information regarding the data libraries contained in this release. The XSDIR file is specific to this release and may not work with previous packages. As of the Sept 2004 release (with MCNP5_RSICC_1.30), the default continuous energy neutron transport data for 15 isotopes are from the t16_2003 library (pre ENDF/B-VII evaluations from Los Alamos Group T-16). For isotopes not available in t16_2003, the neutron data library ACTI (based on ENDF/B-VI, up through and including release 8) is the default, and the ENDF66 library (based on ENDF/B-VI, up through and including release 6) is the default for nuclides not present in either the t16_2003 or the ACTI libraries.
The libraries MCPLIB04 and EL03 are the default libraries for photoatomic and electron transport respectively. SAB2002 is the default library for S(a,b) and LA150U is the default library for photonuclear transport. More information on the data libraries contained in this release is available in Appendix G of the MCNP5 manual or from the data team's web site at
http://www-xdiv.lanl.gov/PROJECTS/DATA/nuclear/
Continuous-energy Neutron Data Libraries
* t16_2003 - pre ENDF/B-VII evaluations from Los Alamos Group T-16 for 15 isotopes
* actia and actib - ENDF/B-VI Release 8
* endf66(a-e) - ENDF/B-VI Release 6
* la150n: 150-MeV Neutron Library for MCNP
* uresa - ENDF/B-VI Release 4 with probability tables
* endf6dn - ENDF/B-VI Release 2 with delayed-neutron data
* endf62mt - multitemperature ENDF/B-VI Release 2
* endf60 - ENDF/B-VI Release 2
* newxs - LANL based evaluations
* rmccs - ENDF/B-V and LANL based evaluations
* rmccsa - ENDF/B-V and LANL based evaluations
* endf5p - ENDFB-V
* endf5u - ENDF/B-V
* misc5xs - Contains a number of previously released small libraries
* kidman - fission product evaluations
* 100xs - LANL based evaluations for a subset of isotopes up to 100 MeV
* endl92 - 1992 ENDL library from Lawrence Livermore National Lab (LLNL)
* endf5mt - Multitemperature data previously released as eprixs and u600k
Discrete Neutron Libraries
Discrete neutron cross sections are used with the DRXS input card in MCNP. The currently supported discrete neutron libraries are:
* newxsd - discrete version of newxs
* drmccs - discrete version of rmccs and rmccsa
* dre5 - discrete version of endf5u and endf5p
Photoatomic Data Libraries
There are now four photoatomic transport data libraries; mcplib, mcplib02, mcplib03, and mcplib04.
MCNP Multigroup Data Libraries
The multigroup neutron and photon library mgxsnp is provided for use with MCNP, and is based primarily on ENDF/B-V evaluations
Photonuclear Data Libraries
We currently support one photonuclear library, la150u.
Thermal Neutron Data Libraries
S(alpha,beta) data are contained in the tmccs, therxs, and sab2002 libraries.
Electron Data Libraries
el and el03 are the electron transport libraries.
Dosimetry Data Libraries
531dos, 532dos, and llldos are the publicly released dosimetry data libraries.
Proton Data Libraries
la150h
The data libraries, as distributed, are in ASCII, or type 1, format.
We refer you to the following web site for available documentation on each library:
http://www-xdiv.lanl.gov/projects/data/nuclear/mcnpdata.html
File: readme_xdata.txt
DATA.tar.gz: MCNPX ascii data libraries
In addition to the standard data libraries for MCNP and MCNPX,
some ascii data libraries specifically for use with MCNPX are
included in this distribution. These data are included
in the MCNP_Nuclear_Data_April2008_?.tgz files and are also
included in the DATA.tar.gz supplemental ascii data file.
atab.dat ----- data required for LAQGSM model / heavy ions
barpol.dat ----- data required for all MCNPX
bcdlib ----- data for PHTLIB to build binary PHTLIB data file
bcdtp ----- data for BERTIN to build binary BERTIN data file
channel1.tab ----- data required for LAQGSM model / heavy ions
cinder.dat ----- data required for depletion/burnup
cindergl.dat ----- data required for delayed gamma lines
el03 ----- electron .03e data library
flalpha.tab ----- data required for INCL4 physics
frldm.tab ----- data required for INCL4 physics
gamman.tbl ----- data required for CEM03 physics
gdr.dat ----- data required for photonuclear models
level.tbl ----- data required for CEM03 physics
mass.tbl ----- data required for CEM03 physics
mcplib03 ----- photon .03p data library
mcplib04 ----- photon .04p data library
pace2.data ----- data required for INCL4 physics
shell.tbl ----- data required for CEM03 physics
vgsld.tab ----- data required for INCL4 physics
specs.all ----- specs file for makxs
xsdir1 ----- xsdir file for makxs with extended AWRs
xsdir_unified ----- xsdir file for makxs from MCNPX5 1.40
For depletion / burnup calculations, the extended "atomic weight ratios"
(AWR) table in xsdir1 is needed. These should be in the new MCNPX 2.6.0
RSICC release xsdir file as well.
Using the xsdir1 and specs.all files, all of the ASCII data libraries
can be converted to binary libraries with the makxs code (provided with
the executable downloads).