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논문 기본 정보

자료유형
학술저널
저자정보
Chen Jiahao (North Carolina State University) Hou Jason (North Carolina State University) Ivanov Kostadin (North Carolina State University)
저널정보
한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제55권 제4호
발행연도
2023.4
수록면
1,428 - 1,438 (11page)
DOI
10.1016/j.net.2022.12.022

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초록· 키워드

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A novel Fission Diffusion Synthetic Acceleration (FDSA) method is developed and implemented as a part of a hybrid neutronics method for source convergence acceleration and variance reduction in Monte Carlo (MC) criticality calculations. The acceleration of the MC calculation stems from constructing a synthetic operator and solving a low-order problem using information obtained from previous MC calculations. By applying the P1 approximation, two correction terms, one for the scalar flux and the other for the current, can be solved in the low-order problem and applied to the transport solution. A variety of one-dimensional (1-D) and two-dimensional (2-D) numerical tests are constructed to demonstrate the performance of FDSA in comparison with the standalone MC method and the coupled MC and Coarse Mesh Finite Difference (MC-CMFD) method on both intended purposes. The comparison results show that the acceleration by a factor of 3–10 can be expected for source convergence and the reduction in MC variance is comparable to CMFD in both slab and full core geometries, although the effectiveness of such hybrid methods is limited to systems with small dominance ratios.

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