Assessment of No-Core-Melt Concept for Pressure Tube Supercritical Water Cooled Reactors under Extreme Accidents

Wu Pan; Ren Yanhao; Shan Jianqiang; Huang Yanping

doi:10.13832/j.jnpe.2021.05.0156

Volume 42 Issue 5

Sep. 2021

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Wu Pan, Ren Yanhao, Shan Jianqiang, Huang Yanping. Assessment of No-Core-Melt Concept for Pressure Tube Supercritical Water Cooled Reactors under Extreme Accidents[J]. Nuclear Power Engineering, 2021, 42(5): 156-161. doi: 10.13832/j.jnpe.2021.05.0156

Citation:

Wu Pan, Ren Yanhao, Shan Jianqiang, Huang Yanping. Assessment of No-Core-Melt Concept for Pressure Tube Supercritical Water Cooled Reactors under Extreme Accidents[J]. Nuclear Power Engineering, 2021, 42(5): 156-161. doi: 10.13832/j.jnpe.2021.05.0156

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Assessment of No-Core-Melt Concept for Pressure Tube Supercritical Water Cooled Reactors under Extreme Accidents

doi: 10.13832/j.jnpe.2021.05.0156

1.
School of Energy and Power Engineering, Xi’an Jiaotong University, Xi’an, 710049, China
2.
CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology, Nuclear Power Institute of China, Chengdu, 610213, China

Received Date: 2020-08-24
Rev Recd Date: 2021-04-21

Available Online: 2021-09-30

Publish Date: 2021-09-30

Abstract

Abstract

This paper develops and verifies the two-dimensional (2D) heat conduction model and radiation heat transfer model based on the self-developed accident analysis code SCTRAN, applies the improved SCTRAN code to the core safety assessment of the Canadian pressure tube supercritical water cooled reactor (PT-SCWR) under the loss-of-coolant accident (LOCA) plus loss of emergency core cooling system (LOECC) accident, and assesses the heat transfer efficiency between the fuel rods and moderator and the key factors. The assessment results show that the residual decay heat of the reactor can be effectively removed by the radiation heat transfer from the fuel rods to fuel channels and the natural convection heat exchange from the fuel rods to steam and that the maximum cladding temperatures of the fuel rods in inner and outer rings of the fuel assembly at the maximum power are 1,278℃ and 1,192℃, respectively, which are below the stainless steel cladding melting temperature. Therefore, no core meltdown occurs throughout the accident.
- LOCA,
- PT-SCWR,
- No-core-melt,
- Radiation heat transfer,
- 2D heat conduction

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References(12)

References

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