Research on radiological consequences analysis of reactor control rod ejection accident based on peak radial average fuel enthalpy rise
The fission products residing in the fuel rod void volume (plenum and pellet-to-cladding gap) are available for release upon cladding breach, and the fission products release fraction is a key parameter for analyzing the radiological consequences of Reactor Control Rod Ejection Accident (REA). Inste...
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| Format: | Article |
| Language: | English |
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KeAi Communications Co., Ltd.
2025-09-01
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| Series: | International Journal of Advanced Nuclear Reactor Design and Technology |
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| Online Access: | http://www.sciencedirect.com/science/article/pii/S2468605025000808 |
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| _version_ | 1849320842495787008 |
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| author | Jie Mao Qiliang Mei Shengqin Gao Dawei Sun Yaru Fu Jiaxin Liu |
| author_facet | Jie Mao Qiliang Mei Shengqin Gao Dawei Sun Yaru Fu Jiaxin Liu |
| author_sort | Jie Mao |
| collection | DOAJ |
| description | The fission products residing in the fuel rod void volume (plenum and pellet-to-cladding gap) are available for release upon cladding breach, and the fission products release fraction is a key parameter for analyzing the radiological consequences of Reactor Control Rod Ejection Accident (REA). Instead of a set of constant release fractions specified in RG 1.183 (2000), RG 1.183 (2023) has been revised the fuel rod gap release fraction to Steady-State Fission Products Release Fraction (SFGR) that are originally residing in the fuel rod gap and Transient Fission Gas Release Fraction (TFGR) that are related to burnup and Radial Average Fuel Enthalpy Rise (△H).This paper specifically analyzes the relationship between the fission products release fraction and △H under different burnup, and a set of relatively conservative calculation dose results are obtained based on the empirical data of a specific power plant. In addition, a sensitivity analysis of the effect of △H on the dose consequences is carried out, and the analysis results show that the dose consequences increases linearly with △H when exceeding the critical conditions capable of causing TFGR. |
| format | Article |
| id | doaj-art-eab2722901e2448db0acfc993acc848b |
| institution | Kabale University |
| issn | 2468-6050 |
| language | English |
| publishDate | 2025-09-01 |
| publisher | KeAi Communications Co., Ltd. |
| record_format | Article |
| series | International Journal of Advanced Nuclear Reactor Design and Technology |
| spelling | doaj-art-eab2722901e2448db0acfc993acc848b2025-08-20T03:49:56ZengKeAi Communications Co., Ltd.International Journal of Advanced Nuclear Reactor Design and Technology2468-60502025-09-017325726310.1016/j.jandt.2025.07.003Research on radiological consequences analysis of reactor control rod ejection accident based on peak radial average fuel enthalpy riseJie Mao0Qiliang Mei1Shengqin Gao2Dawei Sun3Yaru Fu4Jiaxin Liu5Corresponding author.; Shanghai Nuclear Engineering Research and Design Institute CO., LTD., Shanghai 200233, ChinaShanghai Nuclear Engineering Research and Design Institute CO., LTD., Shanghai 200233, ChinaShanghai Nuclear Engineering Research and Design Institute CO., LTD., Shanghai 200233, ChinaShanghai Nuclear Engineering Research and Design Institute CO., LTD., Shanghai 200233, ChinaShanghai Nuclear Engineering Research and Design Institute CO., LTD., Shanghai 200233, ChinaShanghai Nuclear Engineering Research and Design Institute CO., LTD., Shanghai 200233, ChinaThe fission products residing in the fuel rod void volume (plenum and pellet-to-cladding gap) are available for release upon cladding breach, and the fission products release fraction is a key parameter for analyzing the radiological consequences of Reactor Control Rod Ejection Accident (REA). Instead of a set of constant release fractions specified in RG 1.183 (2000), RG 1.183 (2023) has been revised the fuel rod gap release fraction to Steady-State Fission Products Release Fraction (SFGR) that are originally residing in the fuel rod gap and Transient Fission Gas Release Fraction (TFGR) that are related to burnup and Radial Average Fuel Enthalpy Rise (△H).This paper specifically analyzes the relationship between the fission products release fraction and △H under different burnup, and a set of relatively conservative calculation dose results are obtained based on the empirical data of a specific power plant. In addition, a sensitivity analysis of the effect of △H on the dose consequences is carried out, and the analysis results show that the dose consequences increases linearly with △H when exceeding the critical conditions capable of causing TFGR.http://www.sciencedirect.com/science/article/pii/S2468605025000808Reactor control rod ejection accidentRadial average fuel enthalpy riseFuel rod gap release fractionSource termOffsite radiological consequence |
| spellingShingle | Jie Mao Qiliang Mei Shengqin Gao Dawei Sun Yaru Fu Jiaxin Liu Research on radiological consequences analysis of reactor control rod ejection accident based on peak radial average fuel enthalpy rise International Journal of Advanced Nuclear Reactor Design and Technology Reactor control rod ejection accident Radial average fuel enthalpy rise Fuel rod gap release fraction Source term Offsite radiological consequence |
| title | Research on radiological consequences analysis of reactor control rod ejection accident based on peak radial average fuel enthalpy rise |
| title_full | Research on radiological consequences analysis of reactor control rod ejection accident based on peak radial average fuel enthalpy rise |
| title_fullStr | Research on radiological consequences analysis of reactor control rod ejection accident based on peak radial average fuel enthalpy rise |
| title_full_unstemmed | Research on radiological consequences analysis of reactor control rod ejection accident based on peak radial average fuel enthalpy rise |
| title_short | Research on radiological consequences analysis of reactor control rod ejection accident based on peak radial average fuel enthalpy rise |
| title_sort | research on radiological consequences analysis of reactor control rod ejection accident based on peak radial average fuel enthalpy rise |
| topic | Reactor control rod ejection accident Radial average fuel enthalpy rise Fuel rod gap release fraction Source term Offsite radiological consequence |
| url | http://www.sciencedirect.com/science/article/pii/S2468605025000808 |
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