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자료유형
학술저널
저자정보
윤형주 (경희대학교) Do-Yeon Kim (Kyung Hee University) 박광헌 (경희대학교) 홍서기 (경희대학교)
저널정보
한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제48권 제3호
발행연도
2016.6
수록면
624 - 634 (11page)

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Nuclear criticality safety analyses (NCSAs) considering burnup credit were performed forthe GBC-32 cask. The used nuclear fuel assemblies (UNFAs) discharged from Hanbit NuclearPower Plant Unit 3 Cycle 6 were loaded into the cask. Their axial burnup distributionsand average discharge burnups were evaluated using the DeCART and Multi-purposeAnalyzer for Static and Transient Effects of Reactors (MASTER) codes, and NCSAs wereperformed using SCALE 6.1/STandardized Analysis of Reactivity for Burnup Credit usingSCALE (STARBUCS) and Monte Carlo N-Particle transport code, version 6 (MCNP 6). Theaxial burnup distributions were determined for 20 UNFAs with various initial enrichmentsand burnups, which were applied to the criticality analysis for the cask system. The UNFAsfor 20- and 30-year cooling times were assumed to be stored in the cask. The criticalityanalyses indicated that keff values for UNFAs with nonuniform axial burnup distributionswere larger than those with a uniform distribution, that is, the end effects were positive butmuch smaller than those with the reference distribution. The axial burnup distributions for20 UNFAs had shapes that were more symmetrical with a less steep gradient in the upperregion than the reference ones of the United States Department of Energy. These differencesin the axial burnup distributions resulted in a significant reduction in end effectscompared with the reference.

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