Thermo-Hydraulic Research For Supercritical Water Reactor During Power-Raising Phase Of Startup
PROCEEDINGS OF THE 25TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2017, VOL 5(2017)
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.
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关键词
Supercritical, Sliding pressure, startup, Power-raising, Thermo-hydraulic
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