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research-article

Study on Optimization Design for CSR1000 Core

[+] 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

Yang Ping

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
pyangxjtu@gmail.com

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:10.1115/1.4037669 History: Received April 12, 2017; Revised July 31, 2017

Abstract

An optimization design of CSR1000 conceptual core is proposed. Steady state performance of the proposed core is then studied with the SCWR core steady state analysis code system SNTA. These key parameters such as burnup performance, reactivity control capability, power distribution, maximum fuel cladding temperature and maximum linear power density are analyzed. The relative coolant flow rate of the second flow path which is suited with assembly power is also presented. The study shows that the refueling cycle of CSR1000 core can be extended effectively under the optimization design.

Copyright (c) 2017 by ASME
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