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Publications List for John M. McGhee
As of: October, 2002
- Anderson, Matthew, Adrian Gentle, Arkday Kheyfets, John McGhee, and Warner
Miller, "Manifestly Covariant Smoothed Particle Hydrodynamics", in
preparation for submission to Astrophysical Journal, Oct 2002.
- Warsa, James S., Todd Wareing, Jim Morel, John McGhee, and Richard Lehoucq,
"Krylov Subspace Iterations for Deterministic k-Eigenvalue Calculations",
submitted to Nuclear Science and Engineering, Sep, 2002.
- Nathan D. George, Arkday Kheyfets, John M. McGhee, Warner A. Miller,
"Off-Axis Neutrino Scattering in GRB Central Engines" submitted to
Astrophysical Journal, Aug 2002.
- McGhee, John M., "The Dante Boltzmann Transport Solver Project - Technical
Manual and Theoretical Background", Los Alamos National Laboratory internal
report, Jul 2002.
- Morel, J. E., and John M. McGhee, "Spatial Discretizations for Self-Adjoint Forms
of the Radiative Transfer Equations", submitted to Nuclear Science
and Engineering, Jul, 2002.
- McGhee, John M., and Todd A. Wareing, "Attila Version 2: User's Manual"
(LA-UR-00-5778), Mar, 2001. Los Alamos National Laboratory internal report.
- Wareing, T.A., Jim E. Morel and John M. McGhee, ``Coupled
Electron-Photon Transport Methods on 3-D Unstructured Meshes'',
Invited paper at ANS Winter Meeting, Washington D.C. 12-16 Nov, 2000,
(LA-UR-00-3126).
- Wareing, Todd A., John M. McGhee, Jim E. Morel and Shawn D. Pautz,
``Discontinuous Finite Element Sn Methods on 3-D Unstructured Grids,''
Proceedings of International Conference on Mathematics
and Computation, Reactor Physics and Environmental Analysis in Nuclear
Applications, 27-30 September, 1999, Madrid, Spain. Sponsored by
the American Nuclear Society, et. al., Vol. 2, page 1185,
(LA-UR-99-6340). Also, Nuclear Science and Engineering Vol 138, No. 3, July
2001 pp. 256-268.
- Wareing, Todd, A., Jim E. Morel and John M. McGhee, ``A Diffusion
Synthetic Acceleration Method for the Sn Equations with Discontinuous
Finite Element Space and Time Differencing,'' Proceedings of
International Conference on Mathematics
and Computation, Reactor Physics and Environmental Analysis in Nuclear
Applications, 27-30 September, 1999, Madrid, Spain. Sponsored by
the American Nuclear Society, et. al., Vol.1, page 45,
(LA-UR-99-1224).
- Morel, J. E., and J. M. McGhee, `` A Self-Adjoint
Angular Flux Equation'',Nuclear Science and Engineering,
Vol 132, No. 3, Jul 1999, pp. 312-325. LA-UR-98-1781.
- McGhee, J. M., R. M. Roberts, and J. E. Morel,
``The DANTE Boltzmann Transport Solver: An Unstructured
Mesh, 3-D, Spherical Harmonics Algorithm Compatible with
Parallel Computer Architectures'', Proceedings of the
1997 Joint International Conference on Mathematical Methods and
Supercomputing for Nuclear Applications, Saratoga Springs,
New York, October 5-10, 1997 p563-572. Sponsored by the
American Nuclear Society and the OECD Nuclear Energy Agency.
LA-UR-97-1031.
- Morel, J. E., J. M. McGhee, and R. M. Roberts, "DANTE: A
Three-Dimensional, Unstructured Mesh, Finite Element
Transport Code", presented at Organization for Economic
Development (OECD), Nuclear Energy Agency (NEA), Seminar
on 3D Deterministic Radiation Transport Computer Programs,
Paris, France, 2-3 Dec 1996.
- Wareing, T. A., J. M. McGhee, and J. E. Morel, " ATTILA: A
Three-Dimensional Unstructured Tetrahedral Mesh Discrete-Ordinates
Transport Code", presented at the American Nuclear Society
Annual Winter Meeting, Washington, D.C., 10-14 Nov 1996.
Trans. Amer. Nucl. Soc. Vol. 75, p. 146
Also presented at Organization for Economic
Development (OECD), Nuclear Energy Agency (NEA), Seminar
on 3D Deterministic Radiation Transport Computer Programs,
Paris, France, 2-3 Dec 1996
- Morel, J. E., and J. M. McGhee, "Two New 3D Unstructured Mesh
Transport Codes", presented at the 1996 AICHE National Heat Transfer
Conference, 3-6 Aug 1996, Houston, Texas.
- McGhee, J. M.. and J. E. Morel, "NIKE/ATHENA Arbitrary Finite Element
Upgrade", LA-UR-96-2124, Los Alamos National Laboratory, Los Alamos NM,
13 Jun 96.
- Morel, J. E., and J. M. McGhee, "A Diffusion-Synthetic
Acceleration Technique for the Even-Parity S Equations
with Anisotropic Scattering", Nuclear Science and Engineering, Vol.120, No.3, Jul 1995, pp.147-164.
LA-UR-94-1681.
- Morel, J. E., J. M. McGhee, and W. F. Walters, "3-D Research Codes at
Los Alamos", Proceedings of
International Conference on Mathematics and Computations, Reactor Physics,
and Environmental Analysis, Portland Oregon, 30 Apr-4 May 1995.
- Larsen E. W., J. E. Morel, and J. M. McGhee, " Asymptotic Derivation of
the Multigroup P and Simplified SP Equations with Anisotropic
Scatter", Proceedings of
International Conference on Mathematics and Computations, Reactor Physics,
and Environmental Analysis, Portland Oregon, 30 Apr-4 May 1995. Also,
Nuclear Science and Engineering, Vol.123, No.3, Jul 1996, pp.328-342.
- Morel, J. E., J. M. McGhee, and E. W. Larsen, "A 3-D Time-Dependent
Unstructured Tetrahedral Mesh SP Method", Proceedings of
International Conference on Mathematics and Computations, Reactor Physics,
and Environmental Analysis, Portland Oregon, 30 Apr-4 May 1995. Also,
Nuclear Science and Engineering, Vol.123, No.3, Jul 1996, pp.319-327.
- McGhee, J. M.. and J. E. Morel, "NIKE/ATHENA User's Manual",
LA-UR-94-4312, Los Alamos National Laboratory, Los Alamos NM, 5 Dec 94.
- McGhee, J. M.. and J. E. Morel, "NIKE/ATHENA Benchmark Calculations",
LA-UR-94-3765, Los Alamos National Laboratory, Los Alamos NM, 31 Oct 94.
- Morel, J. E., and J. M. McGhee, "A Forward/Adjoint Transport
Formalism for Sensitivity Studies", Proceedings of 6th AIAA/ASME
Thermophysics and Heat Transfer Conference, June 22-23, 1994, Colorado
Springs, Colorado.
- Morel, J. E., and J. M. McGhee, "A Fission-Source Acceleration
Technique for Time-Dependent Even-Parity S Calculations",
Nuclear Science and Engineering, Vol.116, No.2, Feb 1994, pp.147-164.
LA-UR-92-1288.
- Larsen, E. W., J. E. Morel, and J. M. McGhee, "Asymptotic Derivation
of the Simplified P Equations", Proceedings of Joint International
Conference on Mathematical Methods and Supercomputing in Nuclear Applications,
April 19-23, 1993, Karlsruhe, W. Germany.
- Buksa, J. , J. Elson, D. Kothe, J. McGhee, J. Morel, R. Perry, and W. Rider,
"Fully Coupled Neutronic and Hydrodynamic Analysis of Space Nuclear
Reactor Reentry Accidents", Proceedings of the 1993 Simulation
MultiConference, March 29-April 1, 1993, Washington, D.C.
- Morel, J., J. McGhee, and L. Olvey, "Deterministic Three-Dimensional
Nuetron Transport Calculations on the Connection Machine", Copper
Mountain Conference on Iterative Methods, April 9-14, 1992,
Copper Mountain, CO.
- Morel, J. E., J. M. McGhee, L. A. Olvey, and G. W. Claborn, "Solution of
the 3-D Even-Parity S Equations on the Connection Machine",
Proceedings of the International Topical Meeting on
Advances in Mathematics, Computation, and Reactor Physics, April 28 -
May 2, 1991, Pittsburgh, PA, Vol. 1, p 1.1 2-1.
- Morel, J., L. Olvey, G. Claborn and J. McGhee, "Diffusion Accelerated
Solution of the Even-Parity S Equations with Anisotropic Scattering",
American Nuclear Society International Topical Meeting on Advances in
Mathematics, Computations, and Reactor Physics, April 28 - May 2,
1991, Pittsburgh, PA, Vol.3, p 11.2 3-1.
- McGhee, J. M. "A Two Dimensional S DSA Radiation Transport Package
Implemented in a 2D Lagrangian Hydrodynamics Code", Proceedings of
1990 Nuclear Explosives Code Development Conference, Nov 6-9, 1990, Monterey,
CA (Classified)
- El-Genk M., A. Parlos, J. McGhee, S. Lapin, D. Buden, and J. Mims,
"Integrated System Design Optimization for Multimegawatt Space
Nuclear Power Applications", Journal of Propulsion and Power,
Krieger, Melbourne, Fla., Nov-Dec, 1989.
- McGhee, J., M. El-Genk, and R. Rothrock, "An Assesment of Helium Gas
Behavior in SP-100 Class Reactors", Proceedings of the 24th
Intersociety Energy Conversion Engineering Conference, Washington,
D.C., August 6-11, 1989, Vol. 2, p1231-1236, paper 899243. Also
available as Report LA-UR-89-1666, Los Alamos National Laboratory,
Los Alamos, NM, 1989.
- McGhee, J., Gas Production and Behavior in the Coolant of the SP-100
Space Nuclear Power System, Report No. LA-11629-T, Los Alamos National
Laboratory, Los Alamos, New Mexico, August, 1989. (PhD Dissertation,
University of New Mexico, Albuquerque, NM, May, 1989.)
- McGhee, J., M. El-Genk, and R. Rothrock, "Coolant Radiologic Gas Production
in SP-100 Class Reactors", Transactions of the Sixth Symposium
on Space Nuclear Power Systems, Albuquerque, NM, Jan 8-12, 1989,
CONF-890103-Summs., p304-308. Also available as Report LA-UR-88-2210, Los
Alamos National Laboratory, Los Alamos, NM, 1988.
- McGhee, J., M. El-Genk, and R. Rothrock, "Coolant Radiologic Gas Production
in SP-100 Class Reactors", Space Nuclear Power Systems 1989, Orbit,
Malabar, Florida, 1989. Also available as Report LA-UR-89-1200, Los
Alamos National Laboratory, Los Alamos, NM, 1989.
- Parlos, A., M. El-Genk, J. McGhee, D. Buden, and J. Mims, "Energy Conversion
System Optimization Study for Multimegawatt Space Nuclear Power
Applications", IEEE Transactions on Nuclear Science, Vol. 35, No. 3,
June, 1988.
- Parlos, A., M. El-Genk, J. McGhee, D. Buden, and J. Mims, "Energy Conversion
System Optimization Study for Multimegawatt Space Nuclear Power
Application", Transactions of the Fifth Symposium on
Space Nuclear Power Systems, Albuquerque NM, January 11-14, 1988.
- El-Genk, M.S., A. Parlos, J. McGhee, S. Lapin, D. Buden, and J. Mims
"Pellet Bed Reactor Design for Space Power", paper 879360,
22nd Intersociety Energy Conversion Engineering Conference,
Philadelphia PA, 10-14 August 1987.
- Buden, D., M. El-Genk, A. Parlos, J. Mims, J. McGhee, and S. Lapin,
"Pellet Bed Reactor Concept", Final Report prepared for U.S. Department
of Energy under Contract No. DE-AC03-86SF16508 by Science Applications
International Corporation, Albuquerque NM, and University of New Mexico,
Albuquerque NM, March 1987.
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John McGhee
2002-10-04