84
Views
10
CrossRef citations to date
0
Altmetric
Technical Paper

A Review of Legacy and Advanced Self-Shielding Models for Lattice Calculations

Pages 310-320 | Published online: 10 Apr 2017

REFERENCES

  • A. HÉBERT and A. KAVENOKY, “Development of the SPH Homogenization Method,” Proc. Int. Topl. Mtg. Advances in Mathematical Methods for the Solution of Nuclear Engineering Problems, München, Germany, April 27–29, 1981, Vol. 1, p. 195 (1981).
  • D. S. SELENGUT, “Diffusion Coefficients for Heterogeneous Systems,” Trans. Am. Nucl. Soc., 3, 398 (1960).
  • K. KOEBKE, “A New Approach to Homogenization and Group Condensation,” Proc. IAEA Technical Committee Mtg. Homogenization Methods in Reactor Physics, Lugano, Switzerland, November 13–15, 1978, IAEA-TECDOC 231, International Atomic Energy Agency (1978).
  • G. MARLEAU, A. HÉBERT, and R. ROY, “New Computational Methods Used in the Lattice Code Dragon,” Proc. Int. Topl. Mtg. Advances in Reactor Physics, Charleston, South Carolina, March 8–11, 1992, Vol. 1, p. 1–177, American Nuclear Society (1992).
  • R. SANCHEZ and G. C. POMRANING, “A Statistical Analysis of the Double Heterogeneity Problem,” Ann. Nucl. Energy, 18, 371 (1991).
  • A. HÉBERT, “A Collision Probability Analysis of the Double Heterogeneity Problem,” Nucl. Sci. Eng., 115, 177 (1993).
  • R. SANCHEZ, “Renormalized Treatment of the Double Heterogeneity with the Method of Characteristics,” Proc. Int. Topl. Mtg. Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments (PHYSOR-2004), Chicago, Illinois, April 25–29, 2004.
  • J. R. ASKEW, F. J. FAYERS, and P. B. KEMSHELL, “A General Description of the Lattice Code, WIMS,” J. British Energy Soc., 5, 564 (1966).
  • R. J. J. STAMM’LER and M. J. ABBATE, Methods of Steady-State Reactor Physics in Nuclear Design, Academic Press, London (1983).
  • A. HÉBERT and G. MARLEAU, “Generalization of the Stamm’ler Method for the Self-Shielding of Resonant Isotopes in Arbitrary Geometries,” Nucl. Sci. Eng., 108, 230 (1991).
  • A. HÉBERT, “Revisiting the Stamm’ler Self-Shielding Method,” presented at 25th Canadian Nuclear Society Annual Conf., Toronto, Canada, June 6–9, 2004.
  • L. B. LEVITT, “The Probability Tables Method for Treating Unresolved Neutron Resonances in Monte-Carlo Calculations,” Nucl. Sci. Eng., 49, 450 (1972).
  • M. N. NIKOLAEV, “Comments on the Probability Table Method,” Nucl. Sci. Eng., 61, 286 (1976).
  • M. J. HALSALL, “The WIMS Subgroup Method for Resonance Absorption,” Trans. Am. Nucl. Soc., 72, 354 (1995).
  • J. J. CASAL, R. J. J. STAMM’LER, E. A. VILLARINO and A. A. FERRI, “HELIOS: Geometric Capabilities of a New Fuel-Assembly Program,” Proc. Int. Topl. Mtg. Advances in Mathematics, Computation, and Reactor Physics, Pittsburgh, Pennsylvania, April 28–May 2, 1991, Vol. 2, p. 10.21-1, American Nuclear Society (1991).
  • R. E. MACFARLANE and R. M. BOICOURT, “NJOY, A Neutron and Photon Processing System,” Trans. Am. Nucl. Soc., 22, 720 (1975).
  • D. E. CULLEN, “Application of the Probability Table Method to Multigroup Calculations of Neutron Transport,” Nucl. Sci. Eng., 55, 387 (1974).
  • M. J. GRIMSTONE, J. D. TULLETT, and G. RIMPAULT, “Accurate Treatments of Fast Reactor Fuel Assembly Heterogeneity with the ECCO Cell Code,” Proc. Int. Conf. Physics of Reactors: Operation, Design and Computation (PHYSOR 90), Marseille, France, April 23–27, 1990 (1990).
  • P. RIBON, “Statistical Probability Tables. CALENDF Program,” Proc. Seminar on NJOY and THEMIS, Saclay, France, June 20–21, 1989, p. 220, Organization for Economic Cooperation and Development/Nuclear Energy Agency Data Bank (1989).
  • A. HÉBERT and M. COSTE, “Computing Moment-Based Probability Tables for Self-Shielding Calculations in Lattice Codes,” Nucl. Sci. Eng., 142, 245 (2002).
  • A. HÉBERT, “The Ribon Extended Self-Shielding Model,” Nucl. Sci. Eng., 151, 1 (2005).
  • J. ROWLANDS et al., “LWR Pin Cell Benchmark Intercomparisons. An Intercomparison Study Organized by the JEF Project, with Contributions by Britain, France, Germany, The Netherlands, Slovenia and the USA,” JEF Report 15, Organization for Economic Cooperation and Development/Nuclear Energy Agency Data Bank (1999).
  • A. HÉBERT and H. SAYGIN, “Development of DRAGR for the Formatting of DRAGON Cross-Section Libraries,” presented at Seminar on NJOY-91 and THEMIS for the Processing of Evaluated Nuclear Data Files, Saclay, France, April 7–8, 1992, Nuclear Energy Agency Data Bank.
  • J. P. BOTH and Y. PENELIAU, “The Monte Carlo Code TRIPOLI-4 and Its First Benchmark Interpretations,” Proc. Int. Conf. Physics of Reactor (PHYSOR 96), Mito, Japan, 1996.

Reprints and Corporate Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

To request a reprint or corporate permissions for this article, please click on the relevant link below:

Academic Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

Obtain permissions instantly via Rightslink by clicking on the button below:

If you are unable to obtain permissions via Rightslink, please complete and submit this Permissions form. For more information, please visit our Permissions help page.