Analysis of VENUS-2 MOX core measurements with a Monte Carlo code MVP

Proceedings of the PHYSOR 2002 - International Conference on the New Frontiers of Nuclear Technology : Reactor Physics, Safety and High-Performance Computing - The ANS 2002 RPD Topical Meeting

Volumn , Issue , 2002, Pages

  Nagaya, Yasunobu ^a   Okumura, Keisuke ^a   Mori, Takamasa ^a  

^a JAPAN ATOMIC ENERGY AGENCY   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

OXIDE MINERALS; REACTOR CORES; URANIUM DIOXIDE;

ASYMMETRIC EFFECTS; CONTINUOUS ENERGY MONTE CARLO CODE; CORE MEASUREMENTS; EXPERIMENTAL VALUES; MONTE CARLO CODES; NUCLEAR DATA; PIN POWER DISTRIBUTION; RELEASE 5;

MONTE CARLO METHODS;

EID: 84901708562     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (13)

1. A. Charlier, et al., “VENUS International Program (VIP), A Nuclear Data Package for LWR Pu Recycle,” Proc. Int. Conf. Physics of Reactor Operation, Design, and Computation (PHYSOR90), Marseille, France, April 23-26, 1990, Vol. 1, p. VI.65-VI.72 (1990).
2. J. Mondot, et al., “EPICURE: An Experimental Programme devoted to the Validation of the Calculational Schemes for Plutonium Recycling in PWRs,” Proc. Int. Conf. Physics of Reactor Operation, Design, and Computation (PHYSOR90), ), Marseille, France, April 23-26, 1990, Vol. 1, p. VI.53-VI.64 (1990).
3. T. Yamamoto, et al., “Core Physics Experiment of 100% MOX Core: MISTRAL,” Proc. Int. Conf. On Future Nuclear Systems, Global'97, Yokohama, Japan, October 5-10, 1997, Vol. 1, pp.395-400 (1997).
4. K. Sakurada, et al., “STUDIES ON ADVANCED LWR CORES FORE EFFECTIVE USE OF PLUTONIUM AND ANALYSIS OF MOX PHYSICS EXPERIMENTS,” Proc. Int. Conf. On Future Nuclear Systems, Global'99, Jackson Hole, WY, August 29-September 3, 1999, (1999).
5. M. Mori, et al., “CASMO-4/SIMULATE-3 Benchmarking Against High Plutonium Content Pressurized Water Reactor Mixed-Oxide Fuel Critical Experiment,” Nucl. Sci. Eng. 121, pp.41-51 (1995).
6. E. Saji and H. Shirayanagi, “Analysis of Boiling Water Reactor Mixed-Oxide Critical Experiments with CASMO-4/SIMULATE-3,” Nucl. Sci. Eng. 121, pp.52-56 (1995)
7. B. C. Na and E. Sartori, “BLIND BENCHMARK ON THE VENUS-2 MOX CORE MEASUREMENTS,” NEA/SEN/NSC/WPPR(99)2, (1999).
8. B. C. Na and E. Sartori, “BLIND BENCHMARK ON THE 3-D VENUS-2 MOX CORE MEASUREMENTS Final Specification,” NEA/SEN/NSC/WPPR(2001)1, (2001).
9. OECD/NEA, “Benchmark on the VENUS-2 MOX Core Measurements,” NEA/NSC/DOC(2000)7, (2000).
10. T. Mori, et. al., “VECTORIZATION OF CONTINUOUS ENERGY MONTE-CARLO METHOD FOR NEUTRON-TRANSPORT CALCULATION,” J. Nucl. Sci. Technol., 29, pp.325-336 (1992)
11. T. Nakagawa, et. al., “JAPANESE EVALUATED NUCLEAR-DATA LIBRARY VERSION-3 REVISION-2: JENDL-3.2,” J. Nucl. Sci. Technol., 32, pp.1259-1271 (1995)
12. JAERI Nuclear Data Center, "Japanese Evaluated Nuclear Data Library Version 3 Revision 3 (JENDL-3.3)," Private communication (2002).
13. H. Takano, et. al.: “Validation of JENDL-3.3 by Criticality Benchmark Testing,” Proc. Int. Conf. on Nuclear Data for Science and Technology, ND2001, October 7-12, 2001, Tsukuba, JAPAN, in press.