Conceptual Design of Supercritical Water-cooled Reactor CSR150

Ning Zhonghao; Wang Lianjie; Lu Di; Xia Bangyang; Huang Yanping; Chen Xing

doi:10.13832/j.jnpe.2023.S1.0009

Volume 44 Issue S1

Jun. 2023

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Ning Zhonghao, Wang Lianjie, Lu Di, Xia Bangyang, Huang Yanping, Chen Xing. Conceptual Design of Supercritical Water-cooled Reactor CSR150[J]. Nuclear Power Engineering, 2023, 44(S1): 9-13. doi: 10.13832/j.jnpe.2023.S1.0009

Citation:

Ning Zhonghao, Wang Lianjie, Lu Di, Xia Bangyang, Huang Yanping, Chen Xing. Conceptual Design of Supercritical Water-cooled Reactor CSR150[J]. Nuclear Power Engineering, 2023, 44(S1): 9-13. doi: 10.13832/j.jnpe.2023.S1.0009

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Conceptual Design of Supercritical Water-cooled Reactor CSR150

doi: 10.13832/j.jnpe.2023.S1.0009

1.
Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China
2.
CNNC Key Laboratory Thermal-Hydraulics Technology, Nuclear Power Institute of China, Chengdu, 610213, China
3.
Nuclear Power Institute of China, Chengdu, 610213, China

Received Date: 2023-03-04
Rev Recd Date: 2023-04-05
Publish Date: 2023-06-15

Abstract

Abstract

Supercritical water-cooled reactor (SCWR) is regarded as one of the GEN IV nuclear reactors. Based on the conceptual design of CSR1000 proposed by NPIC, the conceptual design of supercritical water-cooled demonostration reactor CSR150 is proposed. The core design of CSR150 is studied in this paper. The core consists of 45 fuel assembles, and the fuel enrichment zoning and two-pass coolant flow scheme are adopted to increase the coolant outlet temperature and reduce the fuel cladding temperature. The study shows that the key parameters such as power distribution and fuel clad temperature meet the design objectives and criteria of CSR150.
- SCWR,
- CSR1000,
- CSR150

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References(6)

References

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