Heat pipe failure accident analysis of a new type of megawatt heat pipe reactor
BackgroundHeat pipe cooled reactors (HPR) have good inherent safety. In the early stage of core design, heat pipe failure accident is usually one of the design basis accidents that need to be considered.PurposeThis study aims to analyze the neutronic-thermalhydraulic coupling performance of a new ty...
| Main Authors: | , , , , , , |
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| Format: | Article |
| Language: | zho |
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Science Press
2022-11-01
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| Series: | He jishu |
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| Online Access: | https://www.hjs.sinap.ac.cn/thesisDetails#10.11889/j.0253-3219.2022.hjs.45.110604&lang=zh |
| _version_ | 1811169663806078976 |
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| author | WANG Zhenlan GOU Junli XU Shihao WANG Zheng SHAN Jianqiang GUO Simao TANG Bin |
| author_facet | WANG Zhenlan GOU Junli XU Shihao WANG Zheng SHAN Jianqiang GUO Simao TANG Bin |
| author_sort | WANG Zhenlan |
| collection | DOAJ |
| description | BackgroundHeat pipe cooled reactors (HPR) have good inherent safety. In the early stage of core design, heat pipe failure accident is usually one of the design basis accidents that need to be considered.PurposeThis study aims to analyze the neutronic-thermalhydraulic coupling performance of a new type of megawatt heat pipe reactor.MethodsFirstly the heat pipe cooled reactor system physical models, including the point kinetics model, the core and heat pipe model and radiation heat transfer model for the inner core cavity, were established according to the designed HPR prototype composed of heat pipe stack and supercritical CO2 Brayton cycle system with thermal power of 3.5 MW. Then, the finite element software FLUENT was employed to conduct neutronic-thermalhydraulic coupling calculation for the three-dimensional reactor core under the steady-state and heat pipe failure accidents. Finally, the core safety performance was evaluated by comparing the peak temperature of each component with the melting point of material.Results & ConclusionsThe results show the designed HPR has good safety performance under the steady state and single heat pipe failure. Radiation heat transfer in the core cavity cannot be ignored in the serious cascade three heat pipe failure accident in high power region. Meanwhile, the design cannot withstand cascading four heat pipe failure. By comparing the peak temperature of the multiple heat pipe failure with the peak temperature of the single heat pipe failure, it shows that the design has good inherent safety. |
| first_indexed | 2024-04-10T16:45:59Z |
| format | Article |
| id | doaj.art-de090f591bc7442aa57016c38c89b85d |
| institution | Directory Open Access Journal |
| issn | 0253-3219 |
| language | zho |
| last_indexed | 2024-04-10T16:45:59Z |
| publishDate | 2022-11-01 |
| publisher | Science Press |
| record_format | Article |
| series | He jishu |
| spelling | doaj.art-de090f591bc7442aa57016c38c89b85d2023-02-08T01:05:04ZzhoScience PressHe jishu0253-32192022-11-01451111060411060410.11889/j.0253-3219.2022.hjs.45.1106040253-3219（2022）11-0110-11Heat pipe failure accident analysis of a new type of megawatt heat pipe reactorWANG Zhenlan0GOU Junli1XU Shihao2WANG Zheng3SHAN Jianqiang4GUO Simao5TANG Bin6School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an 710049, ChinaSchool of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an 710049, ChinaSchool of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an 710049, ChinaSchool of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an 710049, ChinaSchool of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an 710049, ChinaInstitute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang 621000, ChinaInstitute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang 621000, ChinaBackgroundHeat pipe cooled reactors (HPR) have good inherent safety. In the early stage of core design, heat pipe failure accident is usually one of the design basis accidents that need to be considered.PurposeThis study aims to analyze the neutronic-thermalhydraulic coupling performance of a new type of megawatt heat pipe reactor.MethodsFirstly the heat pipe cooled reactor system physical models, including the point kinetics model, the core and heat pipe model and radiation heat transfer model for the inner core cavity, were established according to the designed HPR prototype composed of heat pipe stack and supercritical CO2 Brayton cycle system with thermal power of 3.5 MW. Then, the finite element software FLUENT was employed to conduct neutronic-thermalhydraulic coupling calculation for the three-dimensional reactor core under the steady-state and heat pipe failure accidents. Finally, the core safety performance was evaluated by comparing the peak temperature of each component with the melting point of material.Results & ConclusionsThe results show the designed HPR has good safety performance under the steady state and single heat pipe failure. Radiation heat transfer in the core cavity cannot be ignored in the serious cascade three heat pipe failure accident in high power region. Meanwhile, the design cannot withstand cascading four heat pipe failure. By comparing the peak temperature of the multiple heat pipe failure with the peak temperature of the single heat pipe failure, it shows that the design has good inherent safety.https://www.hjs.sinap.ac.cn/thesisDetails#10.11889/j.0253-3219.2022.hjs.45.110604&lang=zhheat pipe cooled reactorheat pipe failure accidentneutronic-thermalhydraulic coupling calculationcascading heat pipe failureinherent safety |
| spellingShingle | WANG Zhenlan GOU Junli XU Shihao WANG Zheng SHAN Jianqiang GUO Simao TANG Bin Heat pipe failure accident analysis of a new type of megawatt heat pipe reactor He jishu heat pipe cooled reactor heat pipe failure accident neutronic-thermalhydraulic coupling calculation cascading heat pipe failure inherent safety |
| title | Heat pipe failure accident analysis of a new type of megawatt heat pipe reactor |
| title_full | Heat pipe failure accident analysis of a new type of megawatt heat pipe reactor |
| title_fullStr | Heat pipe failure accident analysis of a new type of megawatt heat pipe reactor |
| title_full_unstemmed | Heat pipe failure accident analysis of a new type of megawatt heat pipe reactor |
| title_short | Heat pipe failure accident analysis of a new type of megawatt heat pipe reactor |
| title_sort | heat pipe failure accident analysis of a new type of megawatt heat pipe reactor |
| topic | heat pipe cooled reactor heat pipe failure accident neutronic-thermalhydraulic coupling calculation cascading heat pipe failure inherent safety |
| url | https://www.hjs.sinap.ac.cn/thesisDetails#10.11889/j.0253-3219.2022.hjs.45.110604&lang=zh |
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