Supercritical Water-Cooled Fast Reactor Plant System Safety Analysis Code

Supercritical water-cooled fast reactor is onec-through circulation system. At supercritical pressure reactor coolant pump drive all coollant through the core was heated to steam turbine, the reactor core coolant flow is less than boiling water reactor core flow7/1. And there is no recirculation system, this is the most significant different from the current light-water reactor. Supercritical fast reactor and advanced boiling water reactors hace the same security system configuration. The main purpose of the study is to evaluate supercritical fast reactor safety characters in the concept design research stage.Specific to supercritical fast reactor systems characteristics, we establish reasonable physical mathematical mode, and use the FORTRAN program to compiling different supercritical heat transfer equations, and realize automatic choose different equation to calculate in different transient. At the same time improve the main steam temperature control, and make the supercritical fast reactor power system transient analysis code SFPSAC. Using this code, study the most clad surface temperature change and its safety characters in different transient conditions, upward fuel fission channel, downward flow fission fuel channel and blanket fuel channel. Using this code to analyse the loss of feed-water heating, auxiliary feedwater supply system mistake start, lose of the power, feedwater supply control failure transient and accidents with turbine control valve, reactor coolant pump and control rod as supercritical fast reactor control mode, reserch the pressure, power, cooled temperature, the coolant mass flow changes with time and the sensitive parameters effects. As to the failure of feed-water control we also analysis different control mode effect.And we draw the conclusion by research program:Different supercritical heat transfer corelationship have effect on maximum clad surface temperature in different transient accident. Therefor, it is very important to choose supercritical heat transfer corelationship for safety analysis. Different control modes for the transient results is different. The maximum clad surface temperature is within the scope of security in different transient and accident, satisfy safety standards. The coolant density coefficient, doppler coefficient, core flow distribution method and pump coast time sensitivity parameters have great effect on maximum clad surface temperature.