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Volume 38 Issue 5
Feb.  2025
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Wang Lianjie, Zhao Wenbo, Chen Bingde, Yao Dong, Lu Di. Coupled 3-D Neutronics/Thermal-Hydraulics Analysis for SCWR Core Typical Transients[J]. Nuclear Power Engineering, 2017, 38(5): 145-150. doi: 10.13832/j.jnpe.2017.05.0145
Citation: Wang Lianjie, Zhao Wenbo, Chen Bingde, Yao Dong, Lu Di. Coupled 3-D Neutronics/Thermal-Hydraulics Analysis for SCWR Core Typical Transients[J]. Nuclear Power Engineering, 2017, 38(5): 145-150. doi: 10.13832/j.jnpe.2017.05.0145

Coupled 3-D Neutronics/Thermal-Hydraulics Analysis for SCWR Core Typical Transients

doi: 10.13832/j.jnpe.2017.05.0145
  • Received Date: 2016-11-01
  • Rev Recd Date: 2017-03-21
  • Available Online: 2025-02-09
  • Transient performance of CSR1000 core during some typical transients, such as CR ejection and uncontrolled CR withdrawal is analyzed and evaluated with the coupled three dimensional neutronics/thermal-hydraulics SCWR transient analysis code. The 3-D transient analysis shows that the maximum cladding surface temperature retains lower than safety criteria 1260℃ during the process of CR ejection accident, and the maximum cladding surface temperature retains lower than safety criteria 850℃ during the process of uncontrolled CR withdrawal transient. The safety of CSR1000 core can be ensured during the typical transients under the salient fuel temperature and water density reactivity feedback and the essential reactor protection system.

     

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