CAS OpenIR  > 中科院上海应用物理研究所2011-2018年
Development and application of a system analysis code for liquid fueled molten salt reactors based on RELAP5 code
Shi, CB; Cheng, MS; Liu, GM; Cheng, MS (reprint author), Chinese Acad Sci, Shanghai Inst Appl Phys, Shanghai 201800, Peoples R China.
2016
Source PublicationNUCLEAR ENGINEERING AND DESIGN
ISSN0029-5493
Volume305Pages:378-388
Subtype期刊论文
AbstractThe molten salt reactor (MSR) is one of the six advanced reactor concepts declared by the Generation IV International Forum (GIF), which can be characterized by attractive attributes as inherent safety, economical efficiency, natural resource protection, sustainable development and nuclear non-proliferation. It is important to make system safety analysis for nuclear power plant of MSR. In this paper, in order to developing a system analysis code suitable for liquid fueled molten salt reactors, the point kinetics and thermo-hydraulic models as well as the numerical method in thermal-hydraulic transient code Reactor Excursion and Leak Analysis Program (RELAP5) developed at the Idaho National Engineering Laboratory (INEL) for the U.S. Nuclear Regulatory Commission (NRC) are extended and verified by Molten Salt Reactor Experiment (MSRE) experimental benchmarks. And then, four transient scenarios including the load demand change, the primary flow transient, the secondary flow transient and the reactivity transient of the Molten Salt Breeder Reactor (MSBR) are modeled and simulated so as to evaluate the performance of the reactor during the anticipated transient events using the extended RELAP5 code. The results indicate the extended RELAP5 code is effective and well suited to the liquid fueled molten salt reactor, and the MSBR has strong inherent safety characteristics because of its large negative reactivity coefficient. In the future, the extended RELAP5 code will be used to perform transient safety analysis for a liquid fueled thorium molten salt reactor named TMSR-LF developed by the Center for Thorium Molten Salt Reactor System, Chinese Academy of Sciences. (C) 2016 Elsevier B.V. All rights reserved.
DOI10.1016/j.nucengdes.2016.05.034
Indexed BySCI
Language英语
WOS IDWOS:000383003400036
Citation statistics
Cited Times:7[WOS]   [WOS Record]     [Related Records in WOS]
Document Type期刊论文
Identifierhttp://ir.sinap.ac.cn/handle/331007/26472
Collection中科院上海应用物理研究所2011-2018年
Corresponding AuthorCheng, MS (reprint author), Chinese Acad Sci, Shanghai Inst Appl Phys, Shanghai 201800, Peoples R China.
Recommended Citation
GB/T 7714
Shi, CB,Cheng, MS,Liu, GM,et al. Development and application of a system analysis code for liquid fueled molten salt reactors based on RELAP5 code[J]. NUCLEAR ENGINEERING AND DESIGN,2016,305:378-388.
APA Shi, CB,Cheng, MS,Liu, GM,&Cheng, MS .(2016).Development and application of a system analysis code for liquid fueled molten salt reactors based on RELAP5 code.NUCLEAR ENGINEERING AND DESIGN,305,378-388.
MLA Shi, CB,et al."Development and application of a system analysis code for liquid fueled molten salt reactors based on RELAP5 code".NUCLEAR ENGINEERING AND DESIGN 305(2016):378-388.
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