Numerical study on the release and migration behavior of fission gas in a molten LBE pool
The lead-cooled fast reactor (LFR) is one of the most promising fast neutron reactors using molten lead or the lead–bismuth eutectic (LBE) alloy as a coolant. Under postulated severe accidents, the fuel rod of LFR may be damaged, which would cause the release of fission gas, and the migration of fis...
| Main Authors: | , , , , |
|---|---|
| Format: | Article |
| Language: | English |
| Published: |
Frontiers Media S.A.
2022-08-01
|
| Series: | Frontiers in Energy Research |
| Subjects: | |
| Online Access: | https://www.frontiersin.org/articles/10.3389/fenrg.2022.964841/full |
| _version_ | 1811342670721712128 |
|---|---|
| author | Zijun Mai Zichen Zhao Hui Cheng Songbai Cheng Jiyun Zhao |
| author_facet | Zijun Mai Zichen Zhao Hui Cheng Songbai Cheng Jiyun Zhao |
| author_sort | Zijun Mai |
| collection | DOAJ |
| description | The lead-cooled fast reactor (LFR) is one of the most promising fast neutron reactors using molten lead or the lead–bismuth eutectic (LBE) alloy as a coolant. Under postulated severe accidents, the fuel rod of LFR may be damaged, which would cause the release of fission gas, and the migration of fission gas bubbles in the reactor molten pool will affect the release and absorption of radioactive substances in the reactor. In this paper, a three-dimensional numerical study on the release and migration behavior of fission gas in the molten LBE pool of LFR is carried out based on the volume of fluid method. The bubbles are continuously released by gas injection, and the research mainly focuses on the detachment time, the rising velocity, and the size of the bubble when it detaches at the orifice. The coalescence of bubbles is observed, and the acceleration effect of the bubble wake is confirmed. The distribution of the bubble terminal rising velocity with diameter has no simple or linear relationship. The effects of the gas injection velocity, the release depth, and the gas injection angle are studied. A lower gas injection velocity will delay the detachment and reduce the size of the bubble. The increase of release depth tends to release smaller bubbles. The bubbles released from a vertical surface will attach to the wall. The simulations and theoretical analysis are comparable and have similar tendencies. The distribution of the bubble terminal rising velocity with equivalent diameter may predict the migration behavior of bubbles in molten LBE. |
| first_indexed | 2024-04-13T19:14:57Z |
| format | Article |
| id | doaj.art-af4584aaf2cd4271b8d2fe636e684299 |
| institution | Directory Open Access Journal |
| issn | 2296-598X |
| language | English |
| last_indexed | 2024-04-13T19:14:57Z |
| publishDate | 2022-08-01 |
| publisher | Frontiers Media S.A. |
| record_format | Article |
| series | Frontiers in Energy Research |
| spelling | doaj.art-af4584aaf2cd4271b8d2fe636e6842992022-12-22T02:33:42ZengFrontiers Media S.A.Frontiers in Energy Research2296-598X2022-08-011010.3389/fenrg.2022.964841964841Numerical study on the release and migration behavior of fission gas in a molten LBE poolZijun Mai0Zichen Zhao1Hui Cheng2Songbai Cheng3Jiyun Zhao4Sino-French Institute of Nuclear Engineering and Technology, Sun Yat-Sen University, Zhuhai, Guangdong, ChinaReactor Engineering Center/Serious Accident Department, China Nuclear Power Technology Research Institute Co., Ltd., Shenzhen, Guangdong, ChinaSino-French Institute of Nuclear Engineering and Technology, Sun Yat-Sen University, Zhuhai, Guangdong, ChinaSino-French Institute of Nuclear Engineering and Technology, Sun Yat-Sen University, Zhuhai, Guangdong, ChinaDepartment of Mechanical Engineering, City University of Hong Kong, Hong Kong, ChinaThe lead-cooled fast reactor (LFR) is one of the most promising fast neutron reactors using molten lead or the lead–bismuth eutectic (LBE) alloy as a coolant. Under postulated severe accidents, the fuel rod of LFR may be damaged, which would cause the release of fission gas, and the migration of fission gas bubbles in the reactor molten pool will affect the release and absorption of radioactive substances in the reactor. In this paper, a three-dimensional numerical study on the release and migration behavior of fission gas in the molten LBE pool of LFR is carried out based on the volume of fluid method. The bubbles are continuously released by gas injection, and the research mainly focuses on the detachment time, the rising velocity, and the size of the bubble when it detaches at the orifice. The coalescence of bubbles is observed, and the acceleration effect of the bubble wake is confirmed. The distribution of the bubble terminal rising velocity with diameter has no simple or linear relationship. The effects of the gas injection velocity, the release depth, and the gas injection angle are studied. A lower gas injection velocity will delay the detachment and reduce the size of the bubble. The increase of release depth tends to release smaller bubbles. The bubbles released from a vertical surface will attach to the wall. The simulations and theoretical analysis are comparable and have similar tendencies. The distribution of the bubble terminal rising velocity with equivalent diameter may predict the migration behavior of bubbles in molten LBE.https://www.frontiersin.org/articles/10.3389/fenrg.2022.964841/fulllead-cooled fast reactorlead–bismuth eutectic alloybubble migrationVOF methodnuclear safety |
| spellingShingle | Zijun Mai Zichen Zhao Hui Cheng Songbai Cheng Jiyun Zhao Numerical study on the release and migration behavior of fission gas in a molten LBE pool Frontiers in Energy Research lead-cooled fast reactor lead–bismuth eutectic alloy bubble migration VOF method nuclear safety |
| title | Numerical study on the release and migration behavior of fission gas in a molten LBE pool |
| title_full | Numerical study on the release and migration behavior of fission gas in a molten LBE pool |
| title_fullStr | Numerical study on the release and migration behavior of fission gas in a molten LBE pool |
| title_full_unstemmed | Numerical study on the release and migration behavior of fission gas in a molten LBE pool |
| title_short | Numerical study on the release and migration behavior of fission gas in a molten LBE pool |
| title_sort | numerical study on the release and migration behavior of fission gas in a molten lbe pool |
| topic | lead-cooled fast reactor lead–bismuth eutectic alloy bubble migration VOF method nuclear safety |
| url | https://www.frontiersin.org/articles/10.3389/fenrg.2022.964841/full |
| work_keys_str_mv | AT zijunmai numericalstudyonthereleaseandmigrationbehavioroffissiongasinamoltenlbepool AT zichenzhao numericalstudyonthereleaseandmigrationbehavioroffissiongasinamoltenlbepool AT huicheng numericalstudyonthereleaseandmigrationbehavioroffissiongasinamoltenlbepool AT songbaicheng numericalstudyonthereleaseandmigrationbehavioroffissiongasinamoltenlbepool AT jiyunzhao numericalstudyonthereleaseandmigrationbehavioroffissiongasinamoltenlbepool |