Development of TREND dynamics code for molten salt reactors
The Molten Salt Reactor (MSR), one of the six advanced reactor types of the 4th generation nuclear energy systems, has many impressive features including economic advantages, inherent safety and nuclear non-proliferation. This paper introduces a system analysis code named TREND, which is developed a...
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| Format: | Article |
| Language: | English |
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Elsevier
2021-02-01
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| Series: | Nuclear Engineering and Technology |
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| Online Access: | http://www.sciencedirect.com/science/article/pii/S1738573319308046 |
| _version_ | 1818656721267064832 |
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| author | Wen Yu Jian Ruan Long He James Kendrick Yang Zou Hongjie Xu |
| author_facet | Wen Yu Jian Ruan Long He James Kendrick Yang Zou Hongjie Xu |
| author_sort | Wen Yu |
| collection | DOAJ |
| description | The Molten Salt Reactor (MSR), one of the six advanced reactor types of the 4th generation nuclear energy systems, has many impressive features including economic advantages, inherent safety and nuclear non-proliferation. This paper introduces a system analysis code named TREND, which is developed and used for the steady and transient simulation of MSRs. The TREND code calculates the distributions of pressure, velocity and temperature of single-phase flows by solving the conservation equations of mass, momentum and energy, along with a fluid state equation. Heat structures coupled with the fluid dynamics model is sufficient to meet the demands of modeling MSR system-level thermal-hydraulics. The core power is based on the point reactor neutron kinetics model calculated by the typical Runge-Kutta method. An incremental PID controller is inserted to adjust the operation behaviors. The verification and validation of the TREND code have been carried out in two aspects: detailed code-to-code comparison with established thermal-hydraulic system codes such as RELAP5, and validation with the experimental data from MSRE and the CIET facility (the University of California, Berkeley’s Compact Integral Effects Test facility).The results indicate that TREND can be used in analyzing the transient behaviors of MSRs and will be improved by validating with more experimental results with the support of SINAP. |
| first_indexed | 2024-12-17T03:30:05Z |
| format | Article |
| id | doaj.art-1a1133fc5c0043038fa6b5b20daedea8 |
| institution | Directory Open Access Journal |
| issn | 1738-5733 |
| language | English |
| last_indexed | 2024-12-17T03:30:05Z |
| publishDate | 2021-02-01 |
| publisher | Elsevier |
| record_format | Article |
| series | Nuclear Engineering and Technology |
| spelling | doaj.art-1a1133fc5c0043038fa6b5b20daedea82022-12-21T22:05:18ZengElsevierNuclear Engineering and Technology1738-57332021-02-01532455465Development of TREND dynamics code for molten salt reactorsWen Yu0Jian Ruan1Long He2James Kendrick3Yang Zou4Hongjie Xu5Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai, 201800, China; University of Chinese Academy of Sciences, Beijing, 100049, ChinaShanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai, 201800, China; University of Chinese Academy of Sciences, Beijing, 100049, ChinaShanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai, 201800, China; University of Chinese Academy of Sciences, Beijing, 100049, ChinaDepartment of Nuclear Engineering, University of California, Berkeley, 4118, Etcheverry Hall, Berkeley, CA, 94720, USAShanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai, 201800, China; Corresponding author.Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai, 201800, ChinaThe Molten Salt Reactor (MSR), one of the six advanced reactor types of the 4th generation nuclear energy systems, has many impressive features including economic advantages, inherent safety and nuclear non-proliferation. This paper introduces a system analysis code named TREND, which is developed and used for the steady and transient simulation of MSRs. The TREND code calculates the distributions of pressure, velocity and temperature of single-phase flows by solving the conservation equations of mass, momentum and energy, along with a fluid state equation. Heat structures coupled with the fluid dynamics model is sufficient to meet the demands of modeling MSR system-level thermal-hydraulics. The core power is based on the point reactor neutron kinetics model calculated by the typical Runge-Kutta method. An incremental PID controller is inserted to adjust the operation behaviors. The verification and validation of the TREND code have been carried out in two aspects: detailed code-to-code comparison with established thermal-hydraulic system codes such as RELAP5, and validation with the experimental data from MSRE and the CIET facility (the University of California, Berkeley’s Compact Integral Effects Test facility).The results indicate that TREND can be used in analyzing the transient behaviors of MSRs and will be improved by validating with more experimental results with the support of SINAP.http://www.sciencedirect.com/science/article/pii/S1738573319308046Molten salt reactorTransient analysisCode developmentVerification and validation |
| spellingShingle | Wen Yu Jian Ruan Long He James Kendrick Yang Zou Hongjie Xu Development of TREND dynamics code for molten salt reactors Nuclear Engineering and Technology Molten salt reactor Transient analysis Code development Verification and validation |
| title | Development of TREND dynamics code for molten salt reactors |
| title_full | Development of TREND dynamics code for molten salt reactors |
| title_fullStr | Development of TREND dynamics code for molten salt reactors |
| title_full_unstemmed | Development of TREND dynamics code for molten salt reactors |
| title_short | Development of TREND dynamics code for molten salt reactors |
| title_sort | development of trend dynamics code for molten salt reactors |
| topic | Molten salt reactor Transient analysis Code development Verification and validation |
| url | http://www.sciencedirect.com/science/article/pii/S1738573319308046 |
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