丧失慢化剂事故及运输过程钴靶元件温度计算

Cobalt Rodlet Temperature Analysis During Loss of Moderator Accident and Transport

为在秦山三期CANDU-6型重水堆上生产放射性钴源,将秦山三期CANDU-6型重水堆排管容器内的21根不锈钢调节棒改为钴调节棒。钴调节棒在辐照过程中和辐照后都会产生热量。为验证钴靶元件的安全性,使用上海核工程研究设计院自行开发的模拟钴靶元件导热、对流换热和辐射传热等复杂传热过程的程序,对钴靶元件在丧失慢化剂事故及运输过程的温度进行了分析。结果表明,两种情况下钴靶元件最高温度均未超过其熔点。

In order to produce cobalt rodlet in CANDU-6 reactor core of TQNPC,the 21 stainless steel control rods in reactor vessel were changed to cobalt control rods.Since the heat was released from cobalt rodlet during radiation and post-radiation,in order to demonstrate the operation safety,the code self developed by Shanghai Nuclear Engineering Research and Design Institute was used to analyze the cobalt rodlet temperature during loss of moderator accident and transport.The complex heat transfer process including heat conduction,radiation and convection were modeled in the code.The results show that the peak cobalt rodlet temperature doesn＇t exceed the cobalt melt temperature during these two cases.