铀燃料组件的γ辐射水平计算及防护建议  

Calculation of Gamma Dose Rate of Uranium Fuel Component and Suggestions for Protection

作　　者：聂兰强 伊万里 宋芳媛 

机构地区：[1]中国核电工程有限公司郑州分公司,河南 郑州

出　　处：《应用物理》2021年第7期355-361,共7页Applied Physics

摘　　要：铀燃料元件厂操作235U富集度 ≤ 5%的铀物料,在设计和运行中,对操作铀物料的外照射危害,除采取时间和距离防护措施外,通常不采取屏蔽防护措施。本文以铀燃料元件厂组件组装工序为例,对组件辐射源进行分析并计算组件表面剂量率,给出外照射防护建议。文中重点对238U衰变子体234mPa对γ剂量率的影响进行了分析计算。Uranium fuel fabrication facilities operate 235U uranium materials with enrichment less than or equal to 5%. In design and operation, shielding protection measures are usually not taken except for time and distance protection measures. In this paper, taking the assembly process of components in uranium fuel element factory as an example, the radiation source of components is analyzed, the dose rate on the surface of components is calculated, and some suggestions on external radiation protection are given. In this paper, the influence of 243mPa of 238U decay daughter on γ dose rate is analyzed and calculated.

关 键 词：组件 剂量率 衰变子体 韧致辐射 

分 类 号：TP3[自动化与计算机技术—计算机科学与技术]