中国科学院机构知识库网格
Chinese Academy of Sciences Institutional Repositories Grid
Safety analyses of 10 MWth Forced Circulation LBE-cooled Fast Reactor during unprotected transients

文献类型:期刊论文

作者Gu, Zhixing1,2; Wang, Gang1; Wang, Zhen1,2; Song, Yong1; Zhao, Zhumin1
刊名ANNALS OF NUCLEAR ENERGY
出版日期2016-02-01
卷号88期号:页码:112-117
关键词Fclfr Ntc Transient Analysis
DOI10.1016/j.anucene.2015.11.004
文献子类Article
英文摘要In order to evaluate its safety performance, a 10 MWth Forced Circulation LBE-cooled Fast Reactor (FCLFR) was simulated by a Neutronics and Thermal-hydraulics Coupled simulation program (NTC) under three transient accidents which were unprotected transient overpower (MOP), unprotected loss of flow (ULOF) and unprotected loss of heat sink (ULOHS). The simulation results showed that the reactor could survive both ULOF and UTOP transients and a new steady state was re-established without human or active device intervention. The ULOHS simulation showed that the core power could decrease to the decay heat level due to the negative reactivity feedbacks. At the later stage of this transient, the core temperatures increased very slowly, providing sufficient time (at least 4500 s) for the operator to activate the decay heat removal (DHR) system. (c) 2015 Elsevier Ltd. All rights reserved.
WOS关键词TEST BLANKET MODULE ; CONCEPTUAL DESIGN ; MATERIAL SELECTION ; CHINA ; ITER ; SIMULATION ; GENERATION ; BENCHMARK ; SYSTEM
WOS研究方向Nuclear Science & Technology
语种英语
WOS记录号WOS:000367859000013
资助机构Chinese Academy of Sciences(XDA03040000) ; Chinese Academy of Sciences(XDA03040000) ; Chinese Academy of Sciences(XDA03040000) ; Chinese Academy of Sciences(XDA03040000) ; Chinese Academy of Sciences(XDA03040000) ; Chinese Academy of Sciences(XDA03040000) ; Chinese Academy of Sciences(XDA03040000) ; Chinese Academy of Sciences(XDA03040000)
源URL[http://ir.hfcas.ac.cn:8080/handle/334002/31602]  
专题合肥物质科学研究院_中国科学院核能安全技术研究所
作者单位1.Chinese Acad Sci, Key Lab Neutron & Radiat Safety, Inst Nucl Energy Safety Technol, Hefei 230031, Anhui, Peoples R China
2.Univ Sci & Technol China, Hefei 230027, Anhui, Peoples R China
推荐引用方式
GB/T 7714
Gu, Zhixing,Wang, Gang,Wang, Zhen,et al. Safety analyses of 10 MWth Forced Circulation LBE-cooled Fast Reactor during unprotected transients[J]. ANNALS OF NUCLEAR ENERGY,2016,88(无):112-117.
APA Gu, Zhixing,Wang, Gang,Wang, Zhen,Song, Yong,&Zhao, Zhumin.(2016).Safety analyses of 10 MWth Forced Circulation LBE-cooled Fast Reactor during unprotected transients.ANNALS OF NUCLEAR ENERGY,88(无),112-117.
MLA Gu, Zhixing,et al."Safety analyses of 10 MWth Forced Circulation LBE-cooled Fast Reactor during unprotected transients".ANNALS OF NUCLEAR ENERGY 88.无(2016):112-117.

入库方式: OAI收割

来源:合肥物质科学研究院

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