A study on effects of pin cell homogenization in an actual reactor core geometry

Proceedings of the PHYSOR 2000 - ANS International Topical Meeting on Advances in Reactor Physics and Mathematics and Computation into the Next Millennium

Volumn , Issue , 2000, Pages

  Tatsumi, Masahiro ^a,c   Yamamoto, Akio ^a   Kosaka, Shin Ya ^b   Saji, Etsuro ^b  

^a Nuclear Fuel Industries Ltd   (Japan)

^b Toden Software Inc   (Japan)

^c OSAKA UNIVERSITY   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

CALCULATIONS; GEOMETRY; OXIDE MINERALS; REACTION RATES; REACTOR CORES; URANIUM DIOXIDE;

CALCULATION RESULTS; CORE CALCULATIONS; CORE GEOMETRIES; HETEROGENEOUS MODELING; HOMOGENEOUS MODELS; MOX FUEL ASSEMBLY; POWER DISTRIBUTIONS; POWER VARIATIONS;

PRESSURIZED WATER REACTORS;

EID: 0005754921     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (21)

1. J. J. LAUTARD, S. LOUBIERE, and C. FEDONMAGNAUD, “Three Dimensional Pin by Pin Core Diffusion Calculation,” Proc. Int. Topl. Mtg. Advances in Mathematics, Computations, and Reactor Physics, Pittsburgh, Pennsylvania, April 28-May 2, 1991, Vol. 2, p. 6.1 1-1, American Nuclear Society (1991).
2. S. MENGELLE, A. NICOLAS, E. RICHEBOIS, “A New Power Reactor 3D Transport Calculation Scheme using the CRONOS2 and APOLLO2 Codes,” Proc. Int. Conf. Mathematical and Computation, Reactor Physics and Environmental Analysis in Nuclear Applications, Madrid, Vol. 2, p.1047-1054 (Sep. 27-30,1999).
3. C. Fedon-Magnaud, “Pin-by-Pin Transport Calculation with CRONOS Reactor Code,” Proc. Int. Conf. Mathematical and Computation, Reactor Physics and Environmental Analysis in Nuclear Applications, Madrid, Vol. 2, p.1278-1287 (Sep. 27-30,1999).
4. M. TATSUMI and A. YAMAMOTO, “Advanced Reactor Core Analysis by the Object-oriented 3-D Fine Mesh Transport Calculation on Parallel/Distributed Environment,” Proc. Int. Conf. Mathematical and Computation, Reactor Physics and Environmental Analysis in Nuclear Applications, Madrid, Vol. 2, p.1288-1297 (Sep. 27-30,1999).
5. A. HÉBERT and P. BENOIST, “A Consistent Technique for the Global Homogenization of a Pressurized Water Reactor Assembly,” Nucl. Sci. Eng., 109, 360 (1991).
6. J. MONDOT, “Dé termination de constants équivalents pour les calculs de diffusion aux différences finies,” Proc. Specialists’ Mtg. Homogenization Methods in Reactor Physics, Lugano, Switzerland, November 13-15, 1978, IAEA-TECDOC-231, p.389, International Atomic Energy Agency (1980).
7. K. KOEBKE, “A New Approach to Homogenization and Group Condensation,” Proc. Specialists’ Mtg. Homogenization Methods in Reactor Physics, Lugano, Switzerland, November 13-15, 1978, IAEA-TECDOC-231, p.303, International Atomic Energy Agency (1980).
8. A. F. HENRY, B. A. WORLEY, and A. A. MORSHED, “Spatial Homogenization of Diffusion Theory Parameters,” Proc. Specialists’ Mtg. Homogenization Methods in Reactor Physics, Lugano, Switzerland, November 13-15, 1978, IAEA-TECDOC-231, p.275, International Atomic Energy Agency (1980).
9. J. M. ARAGNOES and C. AHNERT, “A Linear Discontinuous Finite Difference Formulation for Synthetic Coarse-Mesh Few-Group Diffusion Calculations,” Nucl. Sci. Eng., 94, 309 (1986).
10. R-T CHIANG, “Leakage Effect on Lattice Homogenization and Core Reactivity,” Trnas. Am. Nucl. Soc., vol 63, p. 422-423 (1991).
11. R-T CHIANG, “Leakage Methods for Homogenized Core Calculations,” Tans. Am. Nucl. Soc., Vol 65, p. 434-435 (1992).
12. F. RAHNEMA and E. M. NICHITA, “Leakage corrected spatial (assembly) homogenization technique,” Ann. Nucl. Energy, Vol. 24, No. 6, p. 447-488 (1997).
13. S. KOSAKA and E. SAJI, “The Characteristics Transport Calculation for a Multi-Assembly System using Neutron Path Linking Technique,” Proc. Int. Conf. Mathematical and Computation, Reactor Physics and Environmental Analysis in Nuclear Applications, Madrid, Vol. 2, p.1760, (Sep. 27-30,1999).
14. M. EDENIUS, B. H. FORSSÈNA, C. GRAGG, “The Physics Model of CASMO-4,” Proc. Int. Topl. Mtg. Advances in Mathematics, Computations, and Reactor Physics, Pittsburgh, Pennsylvania, USA, Vol. 2, p10.11-1, American Nuclear Society, (April 28-May 2, 1991).
15. D. G. KNOTT, “KRAM: A Lattice-Physics Code for Modeling the Detailed Deletion of Gadolinia Isotopes from BWR Fuel Designs”, Ph.D. Thesis, Pennsylvania State University (1991).
16. T. MORI and M. NAKAGAWA, MVP/GMVP: General Purpose Monte Carlo Codes for Neutron and Photon Transport Calculation based on Continuous Energy and Multigroup Methods, JARI-Data/Code 94-007 (1994).
17. R. E. ALCOUFFE, F. W. BRINKLEY, D. R. MORR and R. D. O’ DELL, User’ s Guide for TWODANT: A Code Package for Two-Dimensional, Diffusion-Accelerated, Neutral-Particle Transport, LA-10049-M (1984).
18. A. HÉBERT, “A Consistent Technique for the Pin-by-Pin Homogenization of a Pressurized Water Reactor Assembly,” Nucl. Sci. Eng., 113, 227 (1993).
19. M. TATSUMI and A. YAMAMOTO, “Scope: A Scalable and Flexibile Parallel Algorithm Based on Object-Oriented Approach for Core Calculations,” Proc. Joint Int. Conf. on Mathematical Methods and Supercomputing for Nuclear Applications, Saratoga Springs, New York, Vol. 1, p 191-202 (Oct. 6-10, 1997).
20. M. TATSUMI and A. YAMAMOTO, “Object-Oriented Approach for An Iterative Calculation Method and Its Parallelization with Domain Decomposition Method, Proc. Computing in Object-Oriented Parallel Environments,” Proc. Second International Symposium, ISCOPE 98, Santa Fe, p.1-11 (December 1998).
21. Y. KOMANO, T. TAKEDA and T. SEKIYA, “Improved few-group coarse-mesh method for calculating three-dimensional power distribution in fast breeder reactor,” NEACRP-L-204 (1978).