压水堆乏燃料源项计算与分析  

The Source Term Calculation and Analysis of PWR Spent Fuel

作　　者：苏卓[1] 邹树梁[2] 于涛[1] 谢金森[1] 

机构地区：[1]南华大学核科学技术学院,湖南衡阳421001 [2]南华大学核能经济与管理研究中心,湖南衡阳421001

出　　处：《南华大学学报（自然科学版）》2011年第4期9-12,共4页Journal of University of South China：Science and Technology

基　　金：国防基础科研基金资助项目(B37201100010)

摘　　要：乏燃料后处理车间的高放射性环境会对监测设备产生一定的辐照损伤,影响其使用寿命,降低系统可靠性.本文使用ORIGEN2程序对压水堆燃料组件进行计算,得出一组乏燃料组件中重要核素的放射性活度、光子能谱等数据,计算结果准确可信,可为乏燃料首端处理中电子监测设备的屏蔽设计提供初始源项数据.In spent fuel reprocessing plant,the highly radioactive environment will have a certain radiation damage on monitoring equipments.Therefore,the using life of the equipments will be affected and the system reliability reduced.In this article,we use ORIGEN2 program to calculate the components of PWR fuel,and obtain a group of data about the important radionuclides in spent fuel components,such like radioactivity,photon energy spectra etc.The calculated results are accurate and credible,and it can provide initial source term data for shield design of electronic monitoring equipment in the first-side processing of spent fuel.

关 键 词：乏燃料 源项计算 活度 光子能谱 

分 类 号：TL249[核科学技术—核燃料循环与材料]