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논문 기본 정보

자료유형
학술저널
저자정보
Zhenyu Wang (North China Electric Power University) Shichang Liu (North China Electric Power University) Ding She (Tsinghua University) Yang Su (China Institute of Atomic Energy) Yixue Chen (North China Electric Power University)
저널정보
한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제53권 제2호
발행연도
2021.2
수록면
430 - 438 (9page)
DOI
https://doi.org/10.1016/j.net.2020.07.018

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The spatial distribution of neutron flux or reaction rate was calculated by cell or mesh tally in traditionalMonte Carlo simulation. However, either cell or mesh tally leads to the increase of memory consumptionand simulation time. In this paper, the function expansion tally (FET) method was developed in ReactorMonte Carlo code RMC to solve this problem. The FET method was applied to the tallies of neutron fluxdistributions of uranium block and PWR fuel rod models. Legendre polynomials were used in the axialdirection, while Zernike polynomials were used in the radial direction. The results of flux, calculationtime and memory consumption of different expansion orders were investigated, and compared with themesh tally. Results showed that the continuous distribution of flux can be obtained by FET method. Theflux distributions were consistent with that of mesh tally, while the memory consumption and simulationtime can be effectively reduced. Finally, the convergence analysis of coefficients of polynomialswere performed, and the selection strategy of FET order was proposed based on the statistics uncertaintyof the coefficients. The proposed method can help to determine the order of FET, which was meaningfulfor the efficiency and accuracy of FET method.

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