氚在钠冷快堆中的迁移行为和环境排放途径研究  

作　　者：杨勇[1] 郑继业[2] 王凤龙[1] 杨洪广[1] 方邦城[1] 张强[1] 周培德[1] 

机构地区：[1]中国原子能科学研究院,北京102413 [2]环境保护部核与辐射安全中心,北京100082

出　　处：《科技创新导报》2017年第23期115-118,121,共5页Science and Technology Innovation Herald

摘　　要：氚是核电站源项评价的重要核素,水堆已做了大量研究,但国内尚未对钠冷快堆氚源进行深入研究。本文给出了钠冷快堆中一回路氚的来源分析和计算方法,建立了钠冷快堆中氚的迁移模型,完成了示范快堆系统中氚的分布计算,给出了环境排放量和排放途径。同时为进一步降低环境排放,给出了增加余热排出系统和冷却剂系统除氚的建议。Tritium is a important nuclide of source term,but there is not any code about tritium source term in fast reactor in China.Tritium Source,which enters into primary loop,was studied,and the model of tritium transporting in FBR was established in the paper.According to the distribution of tritium in CFR600,the key route of tritium released to the atmosphere is the route of direct release from DHRS.It is suggested that some measure to remove the tritium from sodium loop or aerator in DHRS would reduce the tritium source term released to the environment effectively.

关 键 词：氚 钠冷快堆 环境源项 

分 类 号：TL3[核科学技术—核技术及应用]