The Research and Development Progress of SCWR

Zang Jinguang; Huang Yanping

doi:10.13832/j.jnpe.2021.06.0001

Volume 42 Issue 6

Dec. 2021

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Zang Jinguang, Huang Yanping. The Research and Development Progress of SCWR[J]. Nuclear Power Engineering, 2021, 42(6): 1-4. doi: 10.13832/j.jnpe.2021.06.0001

Citation:

Zang Jinguang, Huang Yanping. The Research and Development Progress of SCWR[J]. Nuclear Power Engineering, 2021, 42(6): 1-4. doi: 10.13832/j.jnpe.2021.06.0001

Zang Jinguang, Huang Yanping. The Research and Development Progress of SCWR[J]. Nuclear Power Engineering, 2021, 42(6): 1-4. doi: 10.13832/j.jnpe.2021.06.0001

Citation:

Zang Jinguang, Huang Yanping. The Research and Development Progress of SCWR[J]. Nuclear Power Engineering, 2021, 42(6): 1-4. doi: 10.13832/j.jnpe.2021.06.0001

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The Research and Development Progress of SCWR

doi: 10.13832/j.jnpe.2021.06.0001

Nuclear Power Institute of China, Chengdu, 610213, China

Received Date: 2020-10-23
Rev Recd Date: 2020-12-02
Publish Date: 2021-12-09

Abstract

Abstract

Supercritical water cooled reactor (SCWR) is the only water-cooled reactor among the six types of reactors identified by the Generation IV International Forum. This paper describes the technical characteristics of SCWR, reviews the research and development (R&D) process of SCWR in China, and briefly reviews the latest R&D developments of SCWR in Canada, EU, Japan and other countries. Finally, this paper summarizes the technical advantages, technical challenges and development opportunities of SCWR.
- SCWR,
- R&D progress,
- Suggestions and tasks

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References(6)

References

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