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research-article

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, Chengdu, 610213, China; No. 328, Section 1, Changshun Avenue, Shuangliu County, Chengdu, P. R. China
wanglianjie@npic.ac.cn

Lu Di

Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China; No. 328, Section 1, Changshun Avenue, Shuangliu County, Chengdu, P. R. China
ludyhao@126.com

Zhao Wenbo

Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China; No. 328, Section 1, Changshun Avenue, Shuangliu County, Chengdu, P. R. China
zhaowenbo.npic@gmail.com

1Corresponding author.

ASME doi:10.1115/1.4041693 History: Received July 02, 2018; Revised September 29, 2018

Abstract

Transient performance of CSR1000 core during some typical transients, such as CR ejection and uncontrolled CR withdrawal is analyzed and evaluated with the coupled three dimensional neutronics and thermal-hydraulics SCWR transient analysis code. The 3-D transient analysis shows that the maximum cladding surface temperature retains lower than safety criteria 1260? during the process of CR ejection accident, and the maximum cladding surface temperature retains lower than safety criteria 850? 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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