THERMO-HYDRAULIC RESEARCH FOR SUPERCRITICAL WATER REACTOR DURING POWER-RAISING PHASE OF STARTUP

摘要

Thermal characteristics during startup of CSR1000 are directly related to the security of supercritical water reactors. The heat transfer model during power-raising phase is built according to the sliding pressure mode of CSR1000 and thermal characteristics of coolant and moderator are analyzed. The results show that, during the temperature-raising phase of startup, Coolant and moderator temperatures in inner assemblies increase with core power increase only. With increases of core power and feed-water flow rate, Coolant and moderator temperatures remain unchanged during power-raising phase. Thermal properties of the coolant change in the pseudo-critical temperature and the heat transfer deterioration occurs.