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논문 기본 정보

자료유형
학술저널
저자정보
Wu Yiwei (School of Nuclear Science and Engineering Shanghai Jiao Tong University) Song Qufei (School of Nuclear Science and Engineering Shanghai Jiao Tong University) Wang Ruixiang (School of Nuclear Science and Engineering Shanghai Jiao Tong University) Xiao Yao (School of Nuclear Science and Engineering Shanghai Jiao Tong University) Gu Hanyang (School of Nuclear Science and Engineering Shanghai Jiao Tong University) Guo Hui (School of Nuclear Science and Engineering Shanghai Jiao Tong University)
저널정보
한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제55권 제6호
발행연도
2023.6
수록면
2,112 - 2,124 (13page)
DOI
10.1016/j.net.2023.03.006

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With the rise of economic and safety standards for nuclear reactors, new concepts of Gen-IV reactors and modular reactors showed more complex designs that challenge current tools for reactor physics analysis. A Monte Carlo (MC) two-step method was proposed in this work. This calculation scheme uses the continuous-energy MC method to generate multi-group cross-sections from heterogeneous models. The multi-group MC method, which can adapt locally-heterogeneous models, is used in the core calculation step. This calculation scheme is verified using a Gen-IV modular lead-based fast reactor (LFR) benchmark case. The influence of homogenized patterns, scatter approximations, flux separable approximation, and local heterogeneity in core calculation on simulation results are investigated. Results showed that the cross-sections generated using the 3D assembly model with a locally heterogeneous representation of control rods lead to an accurate estimation with less than 270 pcm bias in core reactivity, 0.5% bias in control rod worth, and 1.5% bias on power distribution. The study verified the applicability of multi group cross-sections generated with the MC method for LFR analysis. The study also proved the feasi bility of multi-group MC in core calculation with local heterogeneity, which saves 85% time compared to the continuous-energy MC.

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