压水堆核电厂燃料包壳破损判断准则研究  

Research on Fuel Failures Judgment Criteria for Pressurized Water Reactor Nuclear Power Plant

作　　者：熊军 吕炜枫 郭润春 高耀毅 XIONG Jun;LYU Weifeng;GUO Runchun;GAO Yaoyi(State Key Laboratory of Nuclear Power Safety Monitoring Technology and Equipment,China Nuclear Power Engineering Co.,Ltd,Shenzhen of Guangdong Prov.518172,China)

机构地区：[1]中广核工程有限公司核电安全监控技术与装备国家重点实验室,广东深圳518172

出　　处：《核科学与工程》2023年第6期1273-1280,共8页Nuclear Science and Engineering

摘　　要：燃料包壳为压水堆核电厂放射性包容的第一道屏障。因燃料包壳破损的发生不可避免且其对核安全的影响显著,燃料包壳破损诊断是压水堆核电厂必备的技术。分析了国内外压水堆核电厂燃料包壳破损诊断方法以及存在的问题,提出了根据一回路冷却剂中放化指标判断压水堆核电厂燃料包壳是否发生破损的系列判断准则,并对可能影响诊断结果的因素进行了探讨。基于国内在役核电厂实际的运行数据对判断准则进行了测试,测试结果表明,提出的燃料包壳破损判断准则可准确地诊断燃料包壳破损的发生,且有更广泛的适用性。The cladding of fuel elements in the core of a pressurized water reactor nuclear power plant(PWR) is the first barrier to the radioactive material in the reactor.Fuel failures diagnosis is indispensable for PWR as fuel failure is not inevitable and the impact on the nuclear safety is significant.Base on the research on diagnosis methods of fuel failures for PWR and existing problems of diagnosis methods,the judgment criteria based on radiochemical index of the primary coolant are established to diagnose the fuel failure.The factors that may affect the diagnosis result are also identified and discussed.The operating data of domestic in-service nuclear power plants are used to test the established judgment criteria,and the test result show that,the established judgment criteria of fuel failures can accurately diagnose the occurrence of fuel failure and has a wider applicability.

关 键 词：燃料包壳破损 判断准则 压水堆核电厂 

分 类 号：TL929[核科学技术—核燃料循环与材料]