压水堆核电站燃料包壳破损状态下主系统氚的测量方法  

Study on Measuring Method of Tritium in Main System during Fuel Cladding Breakage of PWR Nuclear Power Plant

作　　者：范柄辰 曹刚 谭海青 FAN Bing-chen;CAO Gang;TAN Hai-qing(Fujian Fuqing Nuclear Power Co.Ltd,Fuqing,Fujian Prov.350318,China)

机构地区：[1]福建福清核电有限公司,福建福清350318

出　　处：《中国核电》2018年第2期259-261,共3页China Nuclear Power

摘　　要：福清核电站2号机组首循环期间燃料包壳发生了破损,释放到冷却剂中的裂变产物是造成氚测量结果波动较大的主要原因。本文给出了压水堆核电站燃料包壳破损状态下氚的建议测量方法,减少了主系统样品中裂变产物对氚测量的影响,提高了氚的分析准确性。During the first cycle of the Unit 2 of Fuqing nuclear power plant,the fuel cladding was damaged,and the fission products released into the coolant were the main reasons for the greater fluctuation of tritium measurement results.A recommended measuring method for tritium in the fuel cladding failure state of PWR nuclear power plant is presented.The influence of fission products in the main system on tritium measurement is reduced,and the accuracy of tritium analysis is improved.

关 键 词：液闪计数器 燃料包壳破损 裂变产物 氚 

分 类 号：TL943[核科学技术—辐射防护及环境保护]