中国科学院机构知识库网格
Chinese Academy of Sciences Institutional Repositories Grid
Numerical investigation of the core outlet temperature fluctuation for the lead-based reactor

文献类型:期刊论文

作者Wang, Lizhi1,2; Wu, Guowei1; Wang, Jin1; Jin, Ming1; Song, Yong1
刊名ANNALS OF NUCLEAR ENERGY
出版日期2018-07-01
卷号117期号:页码:194-201
关键词Temperature fluctuation Lead-based reactor Core outlet
ISSN号0306-4549
DOI10.1016/j.anucene.2018.03.020
英文摘要

The temperature fluctuations induced by incomplete mixing of coolants with different temperature may cause thermal fatigue at the components of the lead-based reactor core outlet. Thus the accurate analysis of the phenomenon is very crucial for reactor safety operation. In this paper, the temperature fluctuations of the lead-based reactor core outlet were simulated by using large eddy simulation (LES) method in the simplified core outlet models. In order to analyze the temperature fluctuation sensitivity for the fuel assembly design parameters, such as the fuel assembly size and the gap between two adjacent fuel assemblies, five geometry models were constructed with different fuel assembly design parameters. The time histories of temperature fluctuations at different monitoring points on the center of three fuel assemblies were obtained. Then the amplitudes and the power spectrum density (PSD) of temperature fluctuations were analyzed, in order to compare temperature fluctuations of different geometry models at the same locations of core outlet. Finally the distribution characteristics of core outlet temperature fluctuations were obtained in axial directions, and the temperature fluctuation sensitivity with fuel assembly parameters was also analyzed based on the amplitudes, PSD and the normalized root-mean square temperature analysis. It is found that the temperature fluctuation intensity is enhanced with the increase of the gap size between adjacent fuel assemblies and the opposite edge width of each fuel assembly. The analysis results could provide important references for optimized design and engineering guidance of lead-based reactor. (C) 2018 Elsevier Ltd. All rights reserved.

WOS关键词CONCEPTUAL DESIGN ; WATER MODEL ; TRIPLE JET
资助项目Natural Science Foundation of Anhui Province of China[1608085ME107]
WOS研究方向Nuclear Science & Technology
语种英语
WOS记录号WOS:000431469900020
出版者PERGAMON-ELSEVIER SCIENCE LTD
源URL[http://ir.hfcas.ac.cn:8080/handle/334002/36344]  
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
通讯作者Wu, Guowei
作者单位1.Chinese Acad Sci, Inst Nucl Energy Safety Technol, Key Lab Neutron & Radiat Safety, 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
Wang, Lizhi,Wu, Guowei,Wang, Jin,et al. Numerical investigation of the core outlet temperature fluctuation for the lead-based reactor[J]. ANNALS OF NUCLEAR ENERGY,2018,117(无):194-201.
APA Wang, Lizhi,Wu, Guowei,Wang, Jin,Jin, Ming,&Song, Yong.(2018).Numerical investigation of the core outlet temperature fluctuation for the lead-based reactor.ANNALS OF NUCLEAR ENERGY,117(无),194-201.
MLA Wang, Lizhi,et al."Numerical investigation of the core outlet temperature fluctuation for the lead-based reactor".ANNALS OF NUCLEAR ENERGY 117.无(2018):194-201.

入库方式: OAI收割

来源:合肥物质科学研究院

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