Moisture Transfer Model and Simulation for Dehumidification of HTGR Core
A large number of carbon materials are adopted in high-temperature gas-cooled reactor (HTGR). These carbon materials mainly include graphite IG-110 and boron-containing carbon material (BC), both of which are typical porous materials and normally absorb moisture. In order to inhibit the chemical cor...
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| Main Authors: | , , , , , , , |
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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/10.1155/2018/4163914 |
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| author | Jun Li Zhenzhong Zhang Yingchao Meng Huaqiang Yin Shengchao Ma Xuedong He Xingtuan Yang Shengyao Jiang |
| author_facet | Jun Li Zhenzhong Zhang Yingchao Meng Huaqiang Yin Shengchao Ma Xuedong He Xingtuan Yang Shengyao Jiang |
| author_sort | Jun Li |
| collection | DOAJ |
| description | A large number of carbon materials are adopted in high-temperature gas-cooled reactor (HTGR). These carbon materials mainly include graphite IG-110 and boron-containing carbon material (BC), both of which are typical porous materials and normally absorb moisture. In order to inhibit the chemical corrosion reaction between core internals materials and moisture, the core needs to be strictly dehumidified before the reactor is put into operation. This paper mainly analyzed the moisture transfer mechanism in these carbon materials. Moisture transfer models were developed, and the dehumidification process of HTR-PM core was simulated. In addition, the influence of working temperature and system pressure on dehumidification was studied as well. |
| format | Article |
| id | doaj-art-a64c3fa819ac437dbc0e4ed31678a447 |
| 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-a64c3fa819ac437dbc0e4ed31678a4472025-02-03T01:21:48ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832018-01-01201810.1155/2018/41639144163914Moisture Transfer Model and Simulation for Dehumidification of HTGR CoreJun Li0Zhenzhong Zhang1Yingchao Meng2Huaqiang Yin3Shengchao Ma4Xuedong He5Xingtuan Yang6Shengyao Jiang7Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University, Beijing 100084, ChinaInstitute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University, Beijing 100084, ChinaInstitute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University, Beijing 100084, ChinaInstitute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University, Beijing 100084, ChinaInstitute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University, Beijing 100084, ChinaInstitute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University, Beijing 100084, ChinaInstitute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University, Beijing 100084, ChinaInstitute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University, Beijing 100084, ChinaA large number of carbon materials are adopted in high-temperature gas-cooled reactor (HTGR). These carbon materials mainly include graphite IG-110 and boron-containing carbon material (BC), both of which are typical porous materials and normally absorb moisture. In order to inhibit the chemical corrosion reaction between core internals materials and moisture, the core needs to be strictly dehumidified before the reactor is put into operation. This paper mainly analyzed the moisture transfer mechanism in these carbon materials. Moisture transfer models were developed, and the dehumidification process of HTR-PM core was simulated. In addition, the influence of working temperature and system pressure on dehumidification was studied as well.http://dx.doi.org/10.1155/2018/4163914 |
| spellingShingle | Jun Li Zhenzhong Zhang Yingchao Meng Huaqiang Yin Shengchao Ma Xuedong He Xingtuan Yang Shengyao Jiang Moisture Transfer Model and Simulation for Dehumidification of HTGR Core Science and Technology of Nuclear Installations |
| title | Moisture Transfer Model and Simulation for Dehumidification of HTGR Core |
| title_full | Moisture Transfer Model and Simulation for Dehumidification of HTGR Core |
| title_fullStr | Moisture Transfer Model and Simulation for Dehumidification of HTGR Core |
| title_full_unstemmed | Moisture Transfer Model and Simulation for Dehumidification of HTGR Core |
| title_short | Moisture Transfer Model and Simulation for Dehumidification of HTGR Core |
| title_sort | moisture transfer model and simulation for dehumidification of htgr core |
| url | http://dx.doi.org/10.1155/2018/4163914 |
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