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Volume 36 Issue 1
Feb.  2025
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FENG Jinjun, ZHOU Kefeng, HU Wei, ZHAN Jiashuo, SHI Junying, CHAI Guohan. TRACE Thermal Hydraulic Model Development of Qinshan Nuclear Power Plant Phase Ⅱ PWR[J]. Nuclear Power Engineering, 2015, 36(1): 124-126. doi: 10.13832/j.jnpe.2015.01.0124
Citation: FENG Jinjun, ZHOU Kefeng, HU Wei, ZHAN Jiashuo, SHI Junying, CHAI Guohan. TRACE Thermal Hydraulic Model Development of Qinshan Nuclear Power Plant Phase Ⅱ PWR[J]. Nuclear Power Engineering, 2015, 36(1): 124-126. doi: 10.13832/j.jnpe.2015.01.0124

TRACE Thermal Hydraulic Model Development of Qinshan Nuclear Power Plant Phase Ⅱ PWR

doi: 10.13832/j.jnpe.2015.01.0124
  • Received Date: 2014-10-15
  • Rev Recd Date: 2015-01-13
  • Available Online: 2025-02-15
  • In order to improve nuclear power plant safety review work, NNSA imported reactor thermal hydraulic best estimate code TRACE from NRC. In this paper, the NPQJVC two-loop PWR thermal hydraulic model is setup and LBLOCA is simulated using TRACE code and engineering modeling assistant code SNAP. The results of simulation are reasonable.

     

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