Development of a Coupled Code for Steady-State Analysis of the Graphite-Moderated Channel Type Molten Salt Reactor
Joint Authors
Cai, Xiangzhou
Guo, Wei
He, Long
Yu, Cheng-Gang
Dai, Ye
Wang, Hai-Ling
Source
Science and Technology of Nuclear Installations
Issue
Vol. 2018, Issue 2018 (31 Dec. 2018), pp.1-10, 10 p.
Publisher
Hindawi Publishing Corporation
Publication Date
2018-07-02
Country of Publication
Egypt
No. of Pages
10
Abstract EN
The molten salt reactor (MSR) is one of the six advanced reactor concepts selected by Generation IV International Forum (GIF) because of its inherent safety and the promising capabilities of TRU transmutation and Th-U breeding.
In this study, a three-dimensional thermal-hydraulic model (3DTH) is developed for evaluating the steady-state performance of the graphite-moderated channel type MSR.
The coupled code is developed by exchanging the power distribution, temperature, and fuel density distribution between SCALE and 3DTH.
Firstly, the thermal-hydraulic model of the coupled code is validated by RELAP5 code.
Then, the mass flow distribution, temperature field, keff, and power density distribution for a conceptual design of the 2MWt experimental molten salt reactor are calculated and analyzed by the coupled code under both normal operating situation and the central fuel assembly partly blocked situation.
The simulated results are conductive to facilitate the understanding of the steady behavior of the graphite-moderated channel type MSR.
American Psychological Association (APA)
He, Long& Yu, Cheng-Gang& Guo, Wei& Dai, Ye& Wang, Hai-Ling& Cai, Xiangzhou. 2018. Development of a Coupled Code for Steady-State Analysis of the Graphite-Moderated Channel Type Molten Salt Reactor. Science and Technology of Nuclear Installations،Vol. 2018, no. 2018, pp.1-10.
https://search.emarefa.net/detail/BIM-1214939
Modern Language Association (MLA)
He, Long…[et al.]. Development of a Coupled Code for Steady-State Analysis of the Graphite-Moderated Channel Type Molten Salt Reactor. Science and Technology of Nuclear Installations No. 2018 (2018), pp.1-10.
https://search.emarefa.net/detail/BIM-1214939
American Medical Association (AMA)
He, Long& Yu, Cheng-Gang& Guo, Wei& Dai, Ye& Wang, Hai-Ling& Cai, Xiangzhou. Development of a Coupled Code for Steady-State Analysis of the Graphite-Moderated Channel Type Molten Salt Reactor. Science and Technology of Nuclear Installations. 2018. Vol. 2018, no. 2018, pp.1-10.
https://search.emarefa.net/detail/BIM-1214939
Data Type
Journal Articles
Language
English
Notes
Includes bibliographical references
Record ID
BIM-1214939
