Analyses of mistral and epicure experiments with SRAC and MVP code systems

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

  Hibi, Koki ^a   Tatsumi, Masahiro ^b   Umano, Takuya ^c   Fushimi, Atsushi ^d   Yamamoto, Toru ^e   Ueji, Masao ^e   Iwata, Yutaka ^e  

^a MITSUBISHI HEAVY INDUSTRIES LTD   (Japan)

^b Nuclear Fuel Industries   (Japan)

^c TOSHIBA CORPORATION   (Japan)

^d HITACHI LTD   (Japan)

^e Nuclear Power Engineering Corp   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

HEAVY METALS; OXIDE MINERALS; URANIUM DIOXIDE;

CALCULATION RESULTS; DIFFUSION CALCULATION; EXPERIMENTAL PROGRAM; EXPERIMENTAL UNCERTAINTY; HEAVY METAL ATOMS; HIGH MODERATION; MONTE CARLO CALCULATION; PLUTONIUM FUEL;

CALCULATIONS;

EID: 67650720213     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (6)

1. Yamamoto, T., et al., “CORE PHYSICS EXPERIMENT OF 100% MOX CORE: MISTRAL,” Proc. of Int. Conf. On Future Nuclear Systems, Global’97, Vol.1, pp395 (1997)
2. Sakurada, K., et al., “STUDY ON ADVANCED LWR CORES FOR EFFECTIVE USE OF PLUTONIUM AND ANALYSIS OF MOX PHYSICS EXPERIMENTS,” Proc. of Int. Conf. On Future Nuclear Systems, Global’99 (1999)
3. Mondot, J., et al., “EPICURE: An Experimental Programme Devoted to Validation of the Calculational Schemes for Plutonium Recycling in PWRs,” Proc. of Int. Conf. Physics of Reactor Operation, Design and Computation, PHYSOR’90, Vol.1 ppVI-53 (1990)
4. Tsuchihashi, K., et al., “Revised SRAC Code System,” JAERI-1302.(1986)
5. Mori, T., et al., “Vectorization of Continuous Energy Monte Carlo Method for Neutron Transport Calculation,” J. Nucl. Sci. Technol., 29, pp325 (1992)
6. Nakagawa, T., et al. “JENDL-3.2,” J. Nucl. Sci. Technol., 32(12), pp1259 (1995)