Research and Development on Thermal Hydraulic and Safety of Supercritical Water-cooled Reactor

Zhao Xuebin; Huang Yanping; Zang Jinguang

doi:10.13832/j.jnpe.2023.05.0223

Volume 44 Issue 5

Oct. 2023

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Zhao Xuebin, Huang Yanping, Zang Jinguang. Research and Development on Thermal Hydraulic and Safety of Supercritical Water-cooled Reactor[J]. Nuclear Power Engineering, 2023, 44(5): 223-231. doi: 10.13832/j.jnpe.2023.05.0223

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Zhao Xuebin, Huang Yanping, Zang Jinguang. Research and Development on Thermal Hydraulic and Safety of Supercritical Water-cooled Reactor[J]. Nuclear Power Engineering, 2023, 44(5): 223-231. doi: 10.13832/j.jnpe.2023.05.0223

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Research and Development on Thermal Hydraulic and Safety of Supercritical Water-cooled Reactor

doi: 10.13832/j.jnpe.2023.05.0223

CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology, Nuclear Power Institute of China, Chengdu, 610213, China

Received Date: 2023-01-16
Rev Recd Date: 2023-07-25
Publish Date: 2023-10-13

Abstract

Abstract

Supercritical water cooled reactor (SCWR) is the only water-cooled reactor among the six advanced reactor types identified by the Generation IV International Forum. Supercritical water has a unique performance in thermal hydraulics due to its utilization as a coolant and unique properties in physical phase. This paper introduces the general requirements of SCWR thermal hydraulics, and describes the basic characteristics of typical thermal hydraulic processes and the main research and development progress at present. Focusing on the SCWR engineering application, this paper puts forward the follow-up research and development tasks and suggestions for future development of SCWR.
- SCWR,
- Thermal hydraulics,
- R&D progress,
- R&D task

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References(45)

References

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