原子能科学技术2018，Vol.52Issue(4)：672-676,5.DOI:10.7538/yzk.2017.youxian.0232
蒙特卡罗共轭输运法计算反应堆压力容器快中子注量率
Calculation of Reactor Pressure Vessel Fast Neutron Fluence Rate via Monte Carlo Adjoint Transport Method
成昱廷 1周琦 1张寅 2朱庆福1
作者信息
- 1. 中国原子能科学研究院反应堆工程技术研究部,北京 102413
- 2. 国家国防科技工业局,北京 100048
- 折叠
摘要
Abstract
In order to ensure the safety and reliability of reactor pressure vessel(RPV) during the lifetime of nuclear power plant, it is very important to theoretically evaluate the fast neutron fluence rate. In this paper, a method of calculating problem of deep penetration using the adjoint transport theory was proposed. The results of this method were compared with the HBR-2benchmark data and the deterministic method results. The results show that the calculation results are in good agreement with the measurement results. The relative errors of reaction rates are mostly less than 10％ and the maximum relative error is less than 35％. The accuracy of more than 70％of the calculated results is better than that of the deterministic method. It shows that the method proposed in this paper to solve the deep penetration of Monte Carlo is effective and accurate.关键词
蒙特卡罗方法/共轭输运/反应堆压力容器/快中子注量率Key words
Monte Carlo method/adjoint transport/reactor pressure vessel/fast neutron fluence rate分类
能源科技引用本文复制引用
成昱廷,周琦,张寅,朱庆福..蒙特卡罗共轭输运法计算反应堆压力容器快中子注量率[J].原子能科学技术,2018,52(4):672-676,5.
