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.
- Nuclear Engineering Division
Thermo-Hydraulic Research for Supercritical Water Reactor During Power-Raising Phase of Startup
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Zichao, L, Tao, Z, Lanyu, Z, Liang, L, Juan, C, & Hongxing, Y. "Thermo-Hydraulic Research for Supercritical Water Reactor During Power-Raising Phase of Startup." Proceedings of the 2017 25th International Conference on Nuclear Engineering. Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues. Shanghai, China. July 2–6, 2017. V005T05A051. ASME. https://doi.org/10.1115/ICONE25-67595
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