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Implementation of functional expansion tally method and order selection strategy in Monte Carlo code RMC

  • Wang, Zhenyu (School of Nuclear Science and Engineering, North China Electric Power University) ;
  • Liu, Shichang (School of Nuclear Science and Engineering, North China Electric Power University) ;
  • She, Ding (Institute of Nuclear and New Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University) ;
  • Su, Yang (Key Laboratory of Nuclear Data, China Institute of Atomic Energy) ;
  • Chen, Yixue (School of Nuclear Science and Engineering, North China Electric Power University)
  • Received : 2020.03.15
  • Accepted : 2020.07.12
  • Published : 2021.02.25

Abstract

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

Keywords

Acknowledgement

This work is partially supported by Project 11905060 by National Natural Science Foundation of China, Project 1204036 by Beijing Municipal Natural Science Foundation and Project No. ARES-2019-03 by Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, China.

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