Mesh-based activation analysis for structural materials in nuclear reactor

被引:0
|
作者
Li L. [1 ,2 ]
Jiang S. [1 ,2 ]
Chen Z. [1 ,2 ]
Yuan X. [1 ,2 ]
Yang C. [1 ,2 ]
Xie J. [1 ,2 ]
Yu T. [1 ,2 ]
机构
[1] School of Nuclear Science and Technology, University of South China, Hengyang
[2] Hunan Engineering & Technology Research Center for Virtual Nuclear Reactor, Hengyang
来源
He Jishu/Nuclear Techniques | 2022年 / 45卷 / 08期
基金
中国国家自然科学基金;
关键词
Mesh-based activation; Nuclear reactor; Rigorous 2-step method; Structure material;
D O I
10.11889/j.0253-3219.2022.hjs.45.080601
中图分类号
学科分类号
摘要
[Background] Nuclear reactor structural material activation analysis is an important part of nuclear reactor radiation safety analysis. The traditional cell-based activation analysis method can not describe the non-uniform spatial activation effect inside the structural material cells, resulting in a large deviation between the activation source and the dose results, so it is necessary to carry out the high-resolution activation analysis method for nuclear reactor structural materials. [Purpose] This study aims to develop a high-resolution activation analysis method for nuclear reactor structural materials based on mesh activation analysis, and establish an integrated mesh-based activation analysis code (MCFisMA). [Methods] First of all, based on Rigorous 2-step method (R2S), Monte Carlo particle transport program MCNP and activation calculation program FISPACT, the mesh-based activation method was used to divide the structural material model into fine spatial mesh, and the activation calculation of each mesh was carried out in turn to realize the precise activation calculation analysis of nuclear reactor structural materials. Then, the MCFisMA was implemented by using the neutron transport method, material activation method and activation-induced dose coupled together. In addition, NUREG/CR-6115 PWR model was used to study the application of high-resolution activation analysis of structural materials. [Results & Conclusions] The correctness and reliability of the proposed method and MCFisMA program is verified with the ITER shutdown dose rate (SDR) benchmark. The method presented in this paper has theoretical significance for improving the calculation accuracy of the activation source term and decay gamma dose field of nuclear reactor structural materials. It provides theoretical and data support for reactor shielding design, overhaul and refueling plan and decommissioning strategy. © 2022 Science Press. All rights reserved.
引用
收藏
相关论文
共 5 条
  • [1] WANG Xiaohu, HU Yifei, LI Jiangbo, Et al., Calculation of radioactive activated source term for decommissioned reactor, Atomic Energy Science and Technology, 48, 5, pp. 893-897, (2014)
  • [2] LU Peng, Novel approach of shutdown dose rate analysis and its application on fusion device, (2018)
  • [3] LI Wei, Development and application of shutdown dose rate calculation code based on cell tally, (2018)
  • [4] XU Shuyan, Application of Monte Carlo method in experimental nuclear physics, (2006)
  • [5] TAN Jie, ZHANG Peng, Comparison and analysis of two algorithms for solving large depletion chains, High Power Laser and Particle Beams, 30, 3, (2018)