乏燃料后处理厂中子探测器屏蔽慢化体设计

Design of Shielding Moderator for Neutron Detector in Spent Fuel Reprocessing Plant

为监测乏燃料后处理厂关键工艺设备中的放射性核素含量,需根据使用环境设计开发专用中子监测仪,屏蔽慢化体的结构设计是中子监测仪是否能够满足监测需求的关键。通过MCNP、Geant4等软件对屏蔽慢化体的材料及尺寸等结构参数进行模拟分析,以有效探测体积内的体统量作为定量分析指标,结合实际工程情况,完成了屏蔽慢化体结构设计,为乏燃料后处理厂专用中子监测仪的开发提供了关键参数。

In order to monitor the radionuclide content in the key process equipment of the spent fuel reprocessing plant,it is necessary to design and develop a special neutron monitor according to the use environment.The structural design of the shielding moderator is the key to whether the neutron monitor can meet the monitoring requirements.Use software such as MCNP and Geant4 to simulate and analyze the structural parameters of the shielding moderator,such as the material and size.Use the volume in the effective detection volume as a quantitative analysis index.Combined with the actual engineering situation,the structure design of the shielding moderator is completed.It provides key parameters for the development of a dedicated neutron monitor for spent fuel reprocessing plants.