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Volume 32 Issue 5
Mar.  2025
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FU Shengwei, ZHOU Chong, XU Zhihong, YANG Yanhua. Thermal Hydraulic Behavior of SCWR Sliding Pressure Startup[J]. Nuclear Power Engineering, 2011, 32(5): 69-74.
Citation: FU Shengwei, ZHOU Chong, XU Zhihong, YANG Yanhua. Thermal Hydraulic Behavior of SCWR Sliding Pressure Startup[J]. Nuclear Power Engineering, 2011, 32(5): 69-74.

Thermal Hydraulic Behavior of SCWR Sliding Pressure Startup

  • Received Date: 2010-05-04
    Available Online: 2025-03-08
  • The modification to ATHLET-SC code is introduced in this paper,which realizes the simulation of trans-critical transients using two-phase model.With the modified code,the thermal-hydraulic dynamic behavior of the mixed SCWR core during the startup process is simulated.The startup process is similar to the design of SCLWR-H sliding pressure startup.The results show that maximum temperature of clad-ding-surface does not exceed 650℃ in the whole startup process,and the sudden change of water properties in the trans-critical transients will not cause harmful influence to the heat transfer of the fuel cladding.

     

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      沈阳化工大学材料科学与工程学院 沈阳 110142

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