某三代堆初级中子源容器性能分析及设计优化改进

Performance Analysis and Design Optimization of Primary Neutron Source Container for a Third-Generation Reactor

初级中子源为反应堆临界前提供足够的初始中子通量,是压水堆首次启动的必要条件。某三代压水堆的中子源屏蔽容器实测表面剂量率较高,一定程度影响了人员和设备安全。为针对性降低辐射水平,用蒙特卡洛方法建立模型计算,对该中子源屏蔽容器性能评估,并结合能谱分析提出屏蔽容器的改进方案。预期在保证体积少量增加、满足运输性能的前提下,可降低99.5%的辐射水平。

Primary Neutron source provides sufficient initial neutron flux for reactor before criticality,which is a necessary condition for the first start-up of PWR.The measured surface dose rate of neutron source shielding container of a third-generation PWR is relatively high,which could affect the safety of personnel and equipment to a certain extent.In order to reduce the radiation level,Monte Carlo method is used to establish a model for calculation,to evaluate the performance of the neutron source shielding container,and to propose an improvement plan for the shielding container in combination with neutron energy spectrum analysis.It is expected to reduce radiation levels by 99.5%while ensuring only a small increase in volume and satisfying transportation performance.