Improvements in Transport Calculations by the Energy-Dependent Fission Spectra and Subgroup Method for Mutual Self-Shielding

REFERENCES

• P. MOSCA and C. MOUNIER, “Adaptive Energy Mesh Constructor for Multigroup Libraries of the Deterministic Transport Code APOLLO2,” Proc. PHYSOR 2008 Topl. Mtg., Interlaken, Switzerland, September 14–19, 2008.
   Google Scholar
• P. MOSCA et al., “An Adaptive Energy Mesh Constructor for Multigroup Library Generation for Transport Codes,” Nucl. Sci. Eng., 167, 40 (2011).
   Web of Science ®Google Scholar
• M. COSTE-DELCLAUX, “GALILEE: A Nuclear Data Processing System for Transport, Depletion and Shielding Codes,” Proc. PHYSOR 2008 Topl. Mtg., Interlaken, Switzerland, September 14–19, 2008.
   Google Scholar
• J. C. TRAMA, “Overview of TRIPOLI-4 Version 7 Continuous-Energy Monte Carlo Transport Code,” Proc. ICAPP 2011 Topl. Mtg., Nice, France, 2011.
   Google Scholar
• G. RIMPAULT, “Algorithmic Features of the ECCO Cell Code for Treating Heterogeneous Fast Reactor Assemblies,” Proc. Int. Conf. Mathematics and Computations, Reactor Physics, and Environmental Analyses, Portland, Oregon, April 30–May 4, 1995, American Nuclear Socity (1995).
   Google Scholar
• A. SANTAMARINA, D. BERNARD, and Y. RUGAMA, “The Jeff-3.1.1 Nuclear Data Library. Validation Results from JEF-2.2 to JEFF-3.1.1,” NEA 6807, Organisation for Economic Co-operation and Development, Nuclear Energy Agency (2009).
   Google Scholar
• R. SANCHEZ et al., “APOLLO2II: A User-Oriented, Portable, Modular Code for Multigroup Transport Assembly Calculations,” Nucl. Sci. Eng., 100, 352 (1988).
   Web of Science ®Google Scholar
• R. SANCHEZ et al., “APOLLO2 Years 2010,” Nucl. Eng. Technol., 42, 474 (2010).
   Web of Science ®Google Scholar
• M. COSTE-DELCLAUX and S. MENGELLE, “Implementation of a Subgroup Method for Self-Shielding Calculations in APOLLO2 Code,” Proc. PHYSOR 1996 Topl. Mtg., Mito, Ibaraki, Japan, 1996.
   Google Scholar
• C. MOUNIER and B. NORMAND, “Fission Source Calculations and its Influence in Criticality Applications,” Proc. PHYSOR 2008 Topl. Mtg., Interlaken, Switzerland, September 14–19, 2008.
   Google Scholar
• H. GOLFIER et al., “APOLLO3: A Common Project of CEA, AREVA and EDF for the Development of a New Deterministic Multi-Purpose Code for Core Physics Analysis,” Proc. Int. Conf. Mathematics, Computational Methods and Reactor Physics, Saratoga Springs, New York, May 3–7, 2009, American Nuclear Society (2009).
   Google Scholar
• R. MacFARLANE, D. MUIR, and D. GEORGE, “NJOY99.0 Code System for Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF/B Data,” PSR480/NTOY99.0, Los Alamos National Laboratory (2000).
   Google Scholar
• J. SUBLET, P. RIBON, and M. COSTE-DELCLAUX, “CALENDF-2005: User Manual,” CEA-R-6131, Commissariat à l’energie atomique (2006).
   Google Scholar
• M. COSTE-DELCLAUX and S. MENGELLE, “New Resonant Mixture Self-Shielding Treatment in the Code APOLLO2,” Proc. PHYSOR 2004—The Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments, Chicago, Illinois, April 25–29, 2004, American Nuclear Society (2004).
   Google Scholar
• M. COSTE-DELCLAUX, A. AGGERY, and N. HUOT, “New Developments in Resonant Mixture Self-Shielding Treatment with APOLLO2 Code and Application to Jules Horowitz Reactor Core Calculation,” Proc. Mathematics and Computation 2005 Topl. Mtg., Avignon, France, 2005.
   Google Scholar
• M. COSTE-DELCLAUX, “Modélisation du phénomène d’autoprotection dans le code de transport multigroupe APOLLO2,” CEA-R-6114, Commissariat à l’energie atomique (2006).
   Google Scholar
• A. HEBERT and M. COSTE-DELCLAUX, “Computing Moment-Based Probability Tables for Self-Shielding Calculations in Lattice Codes,” Nucl. Sci. Eng., 142, 245 (2002).
   Web of Science ®Google Scholar
• International Handbook of Evaluated Criticality Safety Benchmark Experiments, NEA/NSC/DOC/95/0311–11, Nuclear Science Committee, Organisation for Economic Co-operation and Development, Nuclear Energy Agency (2001).
   Google Scholar
• P. SCIORA et al., “A Break Even Oxide Fuel Core for an Innovative French Sodium-Cooled Fast Reactors: Neutronic Studies Results,” Proc. GLOBAL 2009 Topl. Mtg., Paris, France, 2009.
   Google Scholar