Simulation research on decay heat removal system in primary loop of pool-type sodium-cooled fast reactor

The decay heat removal system in pool-type sodium-cooled fast reactor (PSFR) is the passive safety system, which depends on the natural circulation of sodium and air to keep the reactor coolant cooled. In order to verify the characteristics of the heat transfer of decay heat removal system in primary loop for accident condition, the core single-channel model and the flow between fuel assemblies model were established to simulate the decay heat removal system of primary loop and testify the program on station blackout accident, by using fully-implicit second-order upwind scheme and ameliorative Eular method to solve the equations based on FORTRAN. The calculation results show that the program could reflect the transient characteristics of the decay heat removal system, and it could reach excess real-time simulation. (authors)