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VIM
Monte Carlo Neutron/Photon Transport Code
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REFERENCES

  1. L. B. Levitt and R. C. Lewis, "VIM-1, A Nonmultigroup Monte Carlo Code for Analysis of Fast Critical Assemblies", AI-AEC-12951, Atomics International (1970).
  2. E. M. Gelbard and R. E. Prael, "Monte Carlo Work at Argonne National Laboratory", Proc. of the NEACRP Meeting of a Monte Carlo Study Group, July 1-3, 1974, ANL-75-2 (NEA-CRP-L-118), Argonne National Laboratory (1975), p. 201.
  3. Los Alamos Monte Carlo Group, "MCNP-A General Monte Carlo Code for Neutron and Photon Transport, Version 2B", LA-9396-M, Revised, Los Alamos National Laboratory (1981).
  4. M. O. Cohen, et al., "SAM-CE: A Three-dimensional Monte Carlo Code for the Forward Neutron and Forward and Adjoint Gamma Ray Transport equations", MR-7021, Mathematical Applications Group, Inc. (1971).
  5. L. B. Levitt, "The Probability Table Method for Treating Unresolved Resonances in Monte Carlo Criticality Calculations", Trans. Am. Nucl. Soc., 14, 648 (1971) p. 201.
  6. "Multigroup Calculations Using VIM: A User's Guide to ISOVIM", FRA-TM-169, September, 1992.
  7. R. N. Blomquist and E. M. Gelbard, "An Assessment of Existing Klein- Nishina Monte Carlo Sampling Methods", Nucl. Sci. Eng.,83, (1982),p380.
  8. A. M. Forster, "New MCNP Statistical Analyses for Criticality", Proceedings of the Nuclear Criticality Safety Technology Project Workshop, Embedded Topical on Misapplications and Limitations of Monte Carlo Methods Directed Toward Criticality Safety Analyses", San Diego, CA, May 17, 1995.
  9. R. W. Schaefer and X. X. DiFelici, private communication, July, 1987.
  10. M. Halperin, "Almost Linearly Optimum Combination of Unbiased Estimates", Am. Statis. Assoc. J., 56, 36 (1961).
  11. Jerome Spanier and Ely M. Gelbard, "Monte Carlo Principles and Neutron Transport Problems", Addison-Wesley, 1969.
  12. J. M. Otter, "Unicorn -- A Program to Calculate Point Cross Sections from Resonance Parameters", NAA-SR-11980, Vol. VI (June 1966).
  13. J. M. Otter, R. C. Lewis, and L. B. Levitt, "U3R, A Code to Calculate Unresolved Resonance Cross Section Probability Tables", AI-AEC-13024 (July 1972).
  14. R. E. Prael, "Cross Section Preparation for the Continuous-Energy Monte Carlo Code VIM", Proc. Conf. on Nuclear Cross Sections and Technology, NBS SP 425, p. 447 (March 3-7, 1975).
  15. R. E. Prael and H. Henryson, II, "A Comparison of VIM and MC@2-2 -- Two Detailed Solutions of the Neutron Slowing-down Problem", Proc. Conf. on Nuclear Cross Sections and Technology, NBS SP 425, p. 451 (March 3-7, 1975).
  16. H. C. Honeck and D. R. Finch, "FLANGE II (Version 71-1) A Code to Process Thermal neutron Data from an ENDF/B Tape", DP-1278/ENDF-152 (October 1971).
  17. R. N. Blomquist, R. M. Lell, and E. M. Gelbard, "VIM - A Continuous Energy Monte Carlo Code at ANL", ORNL/RSIC-44, April 21-23, 1980.
  18. M. B. Emmett, "MORSE-CG", Advances in Reactor Computations, Proc. of a Topical Meeting, Salt Lake City, March 28-31, 1983.
  19. R. N. Blomquist, "VIM Validation Bibliography", internal memo.
  20. L. J. Milton, "Thermal Neutron Scattering Treatment in the Monte Carlo Code
  21. S. C. Mo, "Multigroup Monte Carlo Calculation with VIM," internal memo, October 2, 1990.
  22. J. L. Vujic, "Modifications and Extensions of ISOVIM on the Sun SPARC station," internal memo, April 19, 1991.
  23. R. Douglas O'Dell, "Standard Interface Files and Procedures for Reactor Physics Codes, Version IV," USDOE Report LA-6941-MS, Los Alamos National Laboratory, September 1977.
  24. K. L. Derstine, "DIF3D: A Code to Solve One-, Two-, and Three-Dimensional Finite-Difference Diffusion Theory Problems," USDOE Report ANL-82-64, April 1984.
  25. M. Edenius and A. Ahlin, "CASMO-3: New Features, Benchmarking, and Advanced Applications," Int'l. Topical Mtg. on Advances in Reactor Physics, Mathematics, and Computations, Paris, April 27-30, 1987.
  26. "CPM-2 Computer Code Manual," EPRI.RP1252-9 Part II, Chapter 6, Vol. 1 (1987).
  27. C. B. Carrico, E.E. Lewis, and G. Palmiotti, "Three-Dimensional Variational Nodal
  28. Transport Methods for Cartesian, Triangular, and Hexagonal Criticality Calculations," Nucl. Sci. Eng. 111, 168-179 (1992).
  29. R.N. Schaefer, P.J. Collins, and E. M. Gelbard, "ANL Solutions to the NEACRP 3-D Neutron Transport Benchmark Problems," NEACRP A-1008, October, 1989.
  30. Jasmina L. Vujic and Roger N. Blomquist, "BWR Assembly Benchmark Solution by ANL General Geometry Transport Codes," Advances in Mathematics, Computations, and Reactor Physics, Pittsburgh, PA, April 28 - May 1, 1991.
  31. J. L. Vujic, "Validation of the GTRAN2 Transport Method for Complex Hexagonal Assembly Geometry," ANS Transactions 64, p. 523 (1991).
  32. G. Palmiotti, C. B. Carrico, and E. E. Lewis, "Variational Nodal Transport Methods with Anisotropic Scattering," to be submitted to Nucl. Sci. Eng. (1992).
  33. E. M. Gelbard, "Pitfalls in Criticality Safety Monte Carlo Computations: The K-effective of the World", DOE Nuclear Criticality Safety Technology Project Workshop, San Diego, CA, May 16-17, 1995.
  34. R. N. Blomquist, "Monte Carlo Analysis of a Loosely Coupled Reactor", DOE Nuclear Criticality Safety Technology Project Workshop, San Diego, CA, May 16-17, 1995.
  35. A. Mohamed and E. M. Gelbard, "Stratified Source-Sampling Techniques for Monte Carlo Eigenvalue Analysis", International Conference on the Physics of Nuclear Science and Technology, Long Island, NY, October 5-8, 1998.
  36. International Handbook of Evaluated Criticality Safety Benchmark Experiments", NEA/NSC/DOC(95)03, OECD.

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A U.S. Department of Energy laboratory managed by UChicago Argonne, LLC
 

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