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Thermo-Hydraulic Research for Supercritical Water Reactor During Power-Raising Phase of Startup

[+] Author Affiliations
Li Zichao, Zhou Tao, Liu Liang, Chen Juan

North China Electric Power University, Beijing, China

Zhou Lanyu

University of South China, Hengyang, China

Yu Hongxing

Science and Technology on Reactor System Design Technology Laboratory, Chengdu, China

Paper No. ICONE25-67595, pp. V005T05A051; 6 pages
  • 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
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 978-0-7918-5783-0
  • Copyright © 2017 by ASME


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.

Copyright © 2017 by ASME



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