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Investigation on Modeling Thermal-Hydraulic System of CPR1000 NPP Based on RELAP5

[+] Author Affiliations
Cong Wang, Danmei Xie, Peng Zhang, Xinggang Yu, Xiuqun Hou

Wuhan University, Wuhan, China

Paper No. ICONE22-31096, pp. V02BT09A049; 4 pages
doi:10.1115/ICONE22-31096
From:
  • 2014 22nd International Conference on Nuclear Engineering
  • Volume 2B: Thermal Hydraulics
  • Prague, Czech Republic, July 7–11, 2014
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 978-0-7918-4591-2
  • Copyright © 2014 by ASME

abstract

Based on the best-estimate program RELAP5/MOD4.0, a full-scope thermal-hydraulic model with reference to CPR1000 nuclear power plant is established in this paper, which includes the thermal-hydraulic systems of conventional island as well as the primary nuclear island which has already been researched in traditional safety analysis. Therefore, this paper mainly details the numerical model of the turbine and other parts of the conventional island thermodynamic system. A comparison between the calculated results in steady-state and the actual data of reactor demonstrates a fine consistency, thus verifying the accuracy and reliability of the model. In addition, the steam parameter changes are numerically simulated during the steam turbine’s off-design operating condition such as back pressure variation and the variation trends are the same as the actual situation of nuclear power plants.

Copyright © 2014 by ASME

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