Development of a Coupled Code for Steady-State Analysis of the Graphite-Moderated Channel Type Molten Salt Reactor
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 dev...
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| Format: | Article |
| Language: | English |
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Wiley
2018-01-01
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| Series: | Science and Technology of Nuclear Installations |
| Online Access: | http://dx.doi.org/10.1155/2018/4053254 |
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| author | Long He Cheng-Gang Yu Wei Guo Ye Dai Hai-Ling Wang Xiang-Zhou Cai |
| author_facet | Long He Cheng-Gang Yu Wei Guo Ye Dai Hai-Ling Wang Xiang-Zhou Cai |
| author_sort | Long He |
| collection | DOAJ |
| description | 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. |
| format | Article |
| id | doaj-art-d6ad3d361bdd45b7ad36027b077ebe07 |
| institution | Kabale University |
| issn | 1687-6075 1687-6083 |
| language | English |
| publishDate | 2018-01-01 |
| publisher | Wiley |
| record_format | Article |
| series | Science and Technology of Nuclear Installations |
| spelling | doaj-art-d6ad3d361bdd45b7ad36027b077ebe072025-02-03T06:14:18ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832018-01-01201810.1155/2018/40532544053254Development of a Coupled Code for Steady-State Analysis of the Graphite-Moderated Channel Type Molten Salt ReactorLong He0Cheng-Gang Yu1Wei Guo2Ye Dai3Hai-Ling Wang4Xiang-Zhou Cai5Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, ChinaShanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, ChinaShanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, ChinaShanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, ChinaShanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, ChinaShanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, ChinaThe 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.http://dx.doi.org/10.1155/2018/4053254 |
| spellingShingle | Long He Cheng-Gang Yu Wei Guo Ye Dai Hai-Ling Wang Xiang-Zhou Cai Development of a Coupled Code for Steady-State Analysis of the Graphite-Moderated Channel Type Molten Salt Reactor Science and Technology of Nuclear Installations |
| title | Development of a Coupled Code for Steady-State Analysis of the Graphite-Moderated Channel Type Molten Salt Reactor |
| title_full | Development of a Coupled Code for Steady-State Analysis of the Graphite-Moderated Channel Type Molten Salt Reactor |
| title_fullStr | Development of a Coupled Code for Steady-State Analysis of the Graphite-Moderated Channel Type Molten Salt Reactor |
| title_full_unstemmed | Development of a Coupled Code for Steady-State Analysis of the Graphite-Moderated Channel Type Molten Salt Reactor |
| title_short | Development of a Coupled Code for Steady-State Analysis of the Graphite-Moderated Channel Type Molten Salt Reactor |
| title_sort | development of a coupled code for steady state analysis of the graphite moderated channel type molten salt reactor |
| url | http://dx.doi.org/10.1155/2018/4053254 |
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