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Research Papers

Coupled Three-Dimensional Neutronics and Thermal-Hydraulics Analysis for SCWR Core Typical Transients

[+] Author and Article Information
Wang Lianjie

Science and Technology on Reactor System
Design Technology Laboratory,
Nuclear Power Institute of China;
No. 328, Section 1, Changshun Avenue,
Chengdu 610213, China
e-mail: wanglianjie@npic.ac.cn

Lu Di

Science and Technology on Reactor System
Design Technology Laboratory,
Nuclear Power Institute of China;
No. 328, Section 1, Changshun Avenue,
Chengdu 610213, China
e-mail: ludyhao@126.com

Zhao Wenbo

Science and Technology on Reactor System
Design Technology Laboratory,
Nuclear Power Institute of China;
No. 328, Section 1, Changshun Avenue,
Chengdu 610213, China
e-mail: zhaowenbo.npic@gmail.com

1Corresponding author.

Manuscript received July 2, 2018; final manuscript received September 29, 2018; published online January 24, 2019. Assoc. Editor: Mark Anderson.

ASME J of Nuclear Rad Sci 5(1), 011010 (Jan 24, 2019) (6 pages) Paper No: NERS-18-1047; doi: 10.1115/1.4041693 History: Received July 02, 2018; Revised September 29, 2018

Transient performance of China supercritical water-cooled reactor (SCWR) with the rated electric power of 1000 MWel (CSR1000) core during some typical transients, such as control rod (CR) ejection and uncontrolled CR withdrawal, is analyzed and evaluated with the coupled three-dimensional neutronics and thermal-hydraulics SCWR transient analysis code. The 3D transient analysis shows that the maximum cladding surface temperature (MCST) retains lower than safety criteria 1260 °C during the process of CR ejection accident, and the MCST retains lower than safety criteria 850 °C 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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References

Ishiwatari, Y. , Oka, Y. , Koshizuka, S. , Yamajji, A. , and Liu, J. , 2005, “Safety of Super LWR, (I) Safety System Design,” J. Nucl. Sci. Technol., 42(11), pp. 927–934. [CrossRef]
Wang, L. , Yang, P. , Lu, D. , and Zhao, W. , 2018, “Study on Optimization Design for CSR1000 Core,” ASME J. Nucl. Eng. Radiat. Sci., 4(1), p. 011013. [CrossRef]
Wang, L. , Zhao, W. , Chen, B. , Yao, D. , and Yang, P. , 2015, “Development of Three Dimensional Transient Analysis Code STTA for SCWR Core,” Ann. Nucl. Energy, 78, pp. 26–32. [CrossRef]
Oka, Y. , Koshizuka, S. , Ishiwatari, Y. , and Yamajji, A. , 2010, Super Light Water Reactors and Super Fast Reactors, Springer, New York, pp. 210–217.

Figures

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Fig. 1

CSR1000 CRs layout

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Fig. 2

Flow chart of SCWR core transient analysis process

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Fig. 3

CRs initial position (HFP, BLX)

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Fig. 4

Core power variation with time (HFP CR ejection)

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Fig. 5

MCST variation with time (HFP CR ejection)

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Fig. 6

Assembly power variation with time (HFP CR ejection)

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Fig. 7

CRs initial position (HZP, 2EFPD)

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Fig. 8

Core power variation with time (HZP CR ejection)

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Fig. 9

MCST variation with time (HZP CR ejection)

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Fig. 10

Assembly power variation with time (HZP CR ejection)

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Fig. 11

Core power variation with time (HFP uncontrolled CR withdrawal)

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Fig. 12

MCST variation with time (HFP uncontrolled CR withdrawal)

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Fig. 13

Assembly power variation with time (HFP uncontrolled CR withdrawal)

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Fig. 14

Core power variation with time (HZP uncontrolled CR withdrawal)

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Fig. 15

MCST variation with time (HZP uncontrolled CR withdrawal)

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Fig. 16

Assembly power variation with time (HZP uncontrolled CR withdrawal)

Tables

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