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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2022.5
- 수록면
- 1,789 - 1,803 (15page)
- DOI
- https://doi.org/10.1016/j.net.2021.10.038
이용수
초록· 키워드
오류제보하기
RAST-F is a new full-core analysis code based on the two-step approach that couples a multi-group crosssection generation Monte-Carlo code MCS and a multi-group nodal diffusion solver. To demonstrate thefeasibility of using MCS/RAST-F for fast reactor analysis, this paper presents the coupled nodal codeverification results for the MET-1000 and CAR-3600 benchmark cores. Three different multi-group crosssection calculation schemes are employed to improve the agreement between the nodal and referencesolutions. The reference solution is obtained by the MCS code using continuous-energy nuclear data.
Additionally, the MCS/RAST-F nodal solution is verified with results based on cross-section generated bycollision probability code TULIP. A good agreement between MCS/RAST-F and reference solution isobserved with less than 120 pcm discrepancy in keff and less than 1.2% root-mean-square error in powerdistribution. This study confirms the two-step approach MCS/RAST-F as a reliable tool for the threedimensional simulation of reactor cores with fast spectrum
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