Proceedings of the Korean Nuclear Society Conference (한국원자력학회:학술대회논문집)
- 1997.05a
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- Pages.65-70
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- 1997
COMPARISON OF CANDU DUPIC PHYSICS CODES WITH MCNP
- Gyuhong Roh (Korea Atomic Energy Research Institute) ;
- Park, Hangbok (Korea Atomic Energy Research Institute)
- Published : 1997.05.01
Abstract
Computational benchmark calculations have been performed for CANDU DUPIC fuel lattice and core using a Monte Carlo code MCNP-4B with ENDF/B-V library. The eigenvalues of the DUPIC fuel lattice have been predicted by an integral transport code WIMS-AECL using ENDF/B-V library for different burnup steps and lattice conditions. The comparison has shown that the eigenvalues match those of MCNP-4B within 0.20%
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