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Primary pump coast-down characteristics analysis in lead cooled fast reactor under loss of flow transient

文献类型：期刊论文

作者Wu, Guowei1,2; Jin, Ming2; Li, Yazhou2
刊名ANNALS OF NUCLEAR ENERGY
出版日期2017-05-01
卷号103期号:无页码:1-9
关键词Coast-down Flow Halving Time (Fht) Lead Cooled Fast Reactor (Lfr) Loss Of Flow (lOf)
DOI10.1016/j.anucene.2016.11.023
文献子类Article
英文摘要The primary pump coast-down characteristics research is very important to ensure reactor safety during power failure events in the lead cooled fast reactor (LFR) design. The primary pump coast-down Flow Halving Time (FHT) effects on a 10 MWth lead-bismuth cooled research reactor with critical and sub critical operation modes were analyzed under loss of flow transient in this paper. Comparison of different coast-down FHT effects on critical and sub-critical reactors was conducted. Moreover, other relevant parameters those may affect the coast-down FHT requirements (e.g. clad temperature limitation and temperature trigger threshold) were analyzed as well. The results showed that: Increasing the primary pump coast-down FHT can decrease the clad peak temperature in lead cooled fast reactor under LOF transient. Both unprotected and protected loss of flow (ULOF and PLOF) transients in critical reactor and ULOF transient in sub-critical reactor were insensitive to coast-down FHT, while PLOF transient in sub-critical reactor was found to be sensitive to the coast-down FHT. The coast-down FHT effects on sub-critical reactor was bigger than critical reactor in the early phase of LOF transient. The primary pump coast-down FHT had little effects on the critical reactor safety under LOF transients. The clad peak temperature of the sub critical reactor under ULOF transient was the only one that exceeded the temperature limitation among these four transients. Raising the clad temperature limit of the sub-critical reactor contributes little to reactor safety under ULOF transient. Measures should be taken to avoid the happening of serious accident, such as ULOF transient in sub-critical reactor. Scram signal setup (e.g. core outlet temperature trigger threshold) would not enhance the safety of lead cooled critical and sub-critical reactors and would not change the coast-down FHT requirements under LOF transient. (C) 2016 Elsevier Ltd. All rights reserved.
WOS关键词ACTIVATION MARTENSITIC STEEL ; DRIVEN HYBRID SYSTEM ; FAST BREEDER REACTOR ; TEST BLANKET MODULE ; CONCEPTUAL DESIGN ; DEVELOPMENT STRATEGY ; MATERIAL SELECTION ; CHINA ; PROGRESS ; ITER
WOS研究方向Nuclear Science & Technology
语种英语
WOS记录号WOS:000397549900001
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) ; 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/334002/31776]  
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.Univ Sci & Technol China, Sch Nucl Sci & Technol, Hefei 230027, Anhui, Peoples R China
2.Chinese Acad Sci, Inst Nucl Energy Safety Technol, Key Lab Neutron & Radiat Safety, Hefei 230031, Anhui, Peoples R China
推荐引用方式
GB/T 7714		 Wu, Guowei,Jin, Ming,Li, Yazhou. Primary pump coast-down characteristics analysis in lead cooled fast reactor under loss of flow transient[J]. ANNALS OF NUCLEAR ENERGY,2017,103(无):1-9.
APA Wu, Guowei,Jin, Ming,&Li, Yazhou.(2017).Primary pump coast-down characteristics analysis in lead cooled fast reactor under loss of flow transient.ANNALS OF NUCLEAR ENERGY,103(无),1-9.
MLA Wu, Guowei,et al."Primary pump coast-down characteristics analysis in lead cooled fast reactor under loss of flow transient".ANNALS OF NUCLEAR ENERGY 103.无(2017):1-9.

入库方式： OAI收割

来源：合肥物质科学研究院

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