船用堆失水事故元件包壳破损温度阈值及气隙释放后果计算研究  

Research on Fuel Cladding Failure Temperature Criteria and Gap Release Radioactive Aftereffect for LOCA of Ship Reactor

作　　者：张帆[1] 张彦招[1] 赵新文[1] 商学利[1] 

机构地区：[1]海军工程大学核能科学与工程系,湖北武汉430033

出　　处：《原子能科学技术》2014年第1期106-112,共7页Atomic Energy Science and Technology

基　　金：国家自然科学基金资助项目(11075212)

摘　　要：针对船用堆特殊安全性要求,对船用堆失水事故包壳破损温度阈值进行研究。摒弃以往的保守假设,采用最佳估算模型,得到合理的温度阈值,并采用MELCOR程序对典型破口事故下包壳破损份额及气隙释放的放射性后果进行了计算。计算结果为评估舱室剂量、保障运行人员安全提供了依据。Aiming at the particular safety requirement of ship reactor ,the research on fuel cladding failure temperature criteria for LOCA was carried out .The conservative assumption was abandoned ,the reasonable fuel cladding failure temperature criteria was gained with the best estimate model , and the fraction of failure and gap release radioactive aftereffect were calculated by MELCOR code .The calculation results can give a reference for evaluating cabin dose and ensuring the safety for operators .

关 键 词：船用堆 包壳破损 气隙释放 放射性后果 

分 类 号：TL334[核科学技术—核技术及应用]