Neutron Transport Models of AEGIS: An Advanced Next-Generation Neutronics Design System

REFERENCES

• A. YAMAJI, Y. OKA, and S. KOSHIZUKA, “Three-Dimensional Core Design of High Temperature Supercritical-Pressure Light Water Reactor with Neutronic and Thermal-Hydraulic Coupling,” J. Nucl. Sci. Technol., 42, 8 (2005).
   Web of Science ®Google Scholar
• T. MORI and M. NAKAGAWA, “MVP/GVMP: General Purpose Monte-Carlo Codes for Neutron and Photon Transport Calculations Based on Continuous Energy and Multi-group Methods,” JAERI-DATA/Code 95-007, Japan Atomic Energy Research Institute (1994).
   Google Scholar
• A. YAMAMOTO, N. SUGIMURA, and T. USHIO, “Calculation Models of AEGIS, An Advanced Neutronics Solver of Next Generation,” Trans. Am. Nucl. Soc., 92, 631 (2005).
   Google Scholar
• N. SUGIMURA, T. USHIO, and A. YAMAMOTO, “Verification Calculations ofAEGIS,AnAdvanced Neutronics Solver of Next Generation,” Trans. Am. Nucl. Soc., 92, 633 (2005).
   Google Scholar
• J. R. ASKEW, “A Characteristics Formulation of the Neutron Transport Equation in Complicated Geometries,” AEEW-M 1108, U.K. Atomic Energy Authority (1972).
   Google Scholar
• D. G. KNOTT and M. EDENIUS, “Validation of the CASMO-4 Transport Solution,” Proc. Int. Conf. Mathematical Methods and Supercomputing in Nuclear Applications, Karlsruhe, Germany, Vol. 2, p. 547 (1993).
   Google Scholar
• A. YAMAMOTO et al., “Convergence Improvement of Coarse Mesh Rebalance Method for Neutron Transport Calculations,” J. Nucl. Sci. Technol., 41, 781 (2004).
   Web of Science ®Google Scholar
• A. YAMAMOTO, “Generalized Coarse-Mesh Rebalance Method for Acceleration of Neutron Transport Calculations,” Nucl. Sci. Eng., 151, 274 (2005).
   Web of Science ®Google Scholar
• T. USHIO, T. TAKEDA, and M. MORI, “Neutron Anisotropic Scattering Effect in Heterogeneous Cell Calculations of Light Water Reactors,” J. Nucl. Sci. Technol., 40, 464 (2003).
   Web of Science ®Google Scholar
• A. YAMAMOTO, “Analyses of Critical Experiments on Tight-Pitched Lattice Cores in Kyoto University Critical Assembly (KUCA),” MS Thesis, Kyoto University (1989) (in Japanese).
   Google Scholar
• T. USHIO, T. TAKEDA, and M. MORI, “The Characteristics and Subgroup Methods in Square Light Water Reactor Cell Calculations,” Nucl. Sci. Eng., 143, 61 (2003).
   Web of Science ®Google Scholar
• M. TABUCHI et al., “Yet Another Optimum Polar Angle Quadrature Set for the Method of Characteristics,” Trans. Am. Nucl. Soc., 93, 506 (2005).
   Google Scholar
• A. LEONARD and C. T. McDANIEL, “Optimal Polar Angles and Weights,” Trans. Am. Nucl. Soc., 73, 171 (1995).
   Google Scholar
• E. A. VILLARINO et al., “HELIOS: Angularly Dependent Collision Probabilities,” Nucl. Sci. Eng., 112, 16 (1992).
   Web of Science ®Google Scholar
• K. S. SMITH and J. D. RHODES, “CASMO-4 Characteristics Method for Two-Dimensional PWR and BWR Core Calculations,” Trans. Am. Nucl. Soc., 83, 322 (2000).
   Google Scholar
• J. T. WEST and M. B. EMMET, “MARS: A Multiple Array System Using Combinatorial Geometry,” Oak Ridge National Laboratory, Radiation Shielding Information Center (Dec. 1980).
   Google Scholar
• Z. WEISS and G. BALL, “Ray-Tracing in Complicated Geometries,” Ann. Nucl. Energy, 18, 483 (1991).
   Web of Science ®Google Scholar
• T. JEVREMOVIC, J. VUJIC, and K. TSUDA, “ANEMONA—A Neutron Transport Code for General Geometry Reactor Assemblies Based on the Method of Characteristics and R-Function Solid Modeler,” Ann. Nucl. Energy, 28, 125 (2001).
   Web of Science ®Google Scholar
• R. SANCHEZ, L. MAO, and S. SANTANDREA, “Treatment of Boundary Conditions in Trajectory-Based Deterministic Transport Methods,” Nucl. Sci. Eng., 140, 23 (2002).
   Web of Science ®Google Scholar
• R. J. J. STAMM’LER and M. J. ABBATE, Method of Steady-State Reactor Physics in Nuclear Design, Academic Press, New York (1983).
   Google Scholar
• “Benchmark on Deterministic Transport Calculations Without Spatial Homogenization,” NEA/NSC/DOC(2003)16, Organisation for Economic Co-operation and Development/Nuclear Energy Agency (2003).
   Google Scholar
• R. ROY, “Anisotropic Scattering for Integral Transport Codes. Part 2: Cyclic Tracking and Its Application to XY Lattices,” Ann. Nucl. Energy, 18, 511 (1991).
   Web of Science ®Google Scholar
• W. W. ENGLE, Jr., “A User’s Manual for ANISN, A One Dimensional Discrete Ordinates Transport Code with Anisotropic Scattering,” K-1693, Oak Ridge National Laboratory (1967).
   Google Scholar