Development of an advanced core analysis system for boiling water reactor designs

Nuclear Technology

Volumn 118, Issue 1, 1997, Pages 3-12

  Maruyama, Hiromi ^a,b   Koyama, Junichi ^a,c   Aoyama, Motoo ^a   Ishii, Kazuya ^a   Zukeran, Atsushi ^a   Kiguchi, Takashi ^a   Nishimura, Akira ^a  

^a HITACHI LTD   (Japan)

^b SHINSHU UNIVERSITY   (Japan)

^c TOHOKU UNIVERSITY   (Japan)

Author keywords

Boiling water reactor; Monte Carlo calculation; Nodal expansion method

Indexed keywords

COMPUTER AIDED DESIGN; COMPUTER SIMULATION; EIGENVALUES AND EIGENFUNCTIONS; MONTE CARLO METHODS; NUCLEAR FUELS; NUCLEAR REACTOR SIMULATORS; REACTOR CORES; THREE DIMENSIONAL COMPUTER GRAPHICS; VECTORS;

FUEL ASSEMBLIES; NODAL EXPANSION METHOD; SOFTWARE PACKAGE COSNEX; SOFTWARE PACKAGE VMONT;

BOILING WATER REACTORS;

EID: 0031118823     PISSN: 00295450     EISSN: None     Source Type: Journal    
DOI: 10.13182/nt97-a35351     Document Type: Article

References (15)

1. A. TOBA, H. KITAMURA, T. MATSUMOTO, T. YAMAMOTO, T. YASUDA, and A. NISHIMURA, "Burnup Extension and Recent R&D Activities in Japanese BWR," Proc. Int. Conf. Design and Safety of Advanced Nuclear Power Plants, Tokyo, Japan, October 25-29, 1992, Vol. II, p. 7-2 (1992).
2. E. SAJI, T. IWAMOTO, H. MARUYAMA, Y. TAHARA, and M. MORI, "Advances in Nuclear Calculational Methods for Commercial Light Water Reactors," Nihon Genshiryoku Gakkaishi, 36, 484 (1994) (in Japanese).
3. T. SHIMOSHIGE, H. UMEHARA, and M. AOYAMA, "Development of Highly Economical BWR Core," Hitachi Review, 41, 217 (1992).
4. T. MOCHIDA, M. NAKAMURA, J. YAMASHITA, H. MARUYAMA, S. MUTO, and S. KASAI, "Operating Experience with the Multienrichment Initial Core of Boiling Water Reactor Kashiwazaki-Kariwa Unit 5," Nucl. Technol., 114, 308 (1996).
5. R. E. McFARLANE and D. W. MUIR, "The NJOY Nuclear Data Processing System, Version 91," LA-12740-M, Los Alamos National Laboratory (1994).
6. R. W. ROUSSIN, P. G. YOUNG, and R. D. McKNIGHT, "Status of the ENDF/B-VI Nuclear Data File," Trans. Am. Nucl. Soc., 73, 425 (1995).
7. Y. KIKUCHI, H. TAKANO, and T. NAKAGAWA, "JENDL-3 Revision 2 - Its Evaluation and Validation," Trans. Am. Nucl. Soc., 73, 424 (1995).
8. Y. MORIMOTO, H. MARUYAMA, K. ISHII, and M. AOYAMA, "Neutronic Analysis Code for Fuel Assembly Using a Vectorized Monte Carlo Method," Nucl. Sci. Eng., 103, 351 (1989).
9. K. ISHII, H. MARUYAMA, and Y. MORIMOTO, "Improvement of Vectorized Monte Carlo Method for Neutron Transport Analysis," J. Nucl. Sci. Technol., 26, 966 (1989).
10. R. T. LAHEY, Jr., and F. J. MOODY, The Thermal Hydraulics of a Boiling Water Nuclear Reactor, American Nuclear Society, LaGrange Park, Illinois (1977).
11. R. D. LAWRENCE, "Progress in Nodal Methods for the Solution of the Neutron Diffusion and Transport Equations," Prog. Nucl. Energy, 17, 271 (1986).
12. J. M. PUTNEY, "A Nodal Expansion Method for Fast Reactor Calculations in Hexagonal Geometry," Ann. Nucl. Energy, 17, 9 (1987).
13. J. KOYAMA and M. AOYAMA, "Nodal Expansion Method for Solution of Diffusion Equation in Hexagonal Geometry," J. Nucl. Sci. Technol., 26, 636 (1989).
14. K. R. REMPE, K. S. SMITH, and A. F. HENRY, "SIMULATE-3 Pin Power Reconstruction: Methods and Benchmarking," Proc. 1988 Int. Reactor Physics Conf., Jackson Hole, Wyoming, September 18-22, 1988, Vol. III, p. 19, American Nuclear Society (1988).
15. P. GRIMM, M. ABOUDY, A. GALPERIN, and M. SEGEV, "A Test of Main Stream Pin Power Reconstruction Methods," Nucl. Sci. Eng., 122, 395 (1996).