Cobalt Rodlet Temperature Analysis During Loss of Moderator Accident and Transport

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.