Analysis on the discharge characteristics and spreading behavior of an ex-vessel core melt in the SMART
The aim of this research is to analyze the characteristics of a core melt discharged from the reactor vessel and the spreading behavior the core melt in the reactor cavity of the SMART. First, a severe accident sequence under conservative conditions is simulated by the MELCOR code to obtain the cond...
| Main Authors: | , , , , , , |
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| Format: | Article |
| Language: | English |
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Elsevier
2022-12-01
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| Series: | Nuclear Engineering and Technology |
| Subjects: | |
| Online Access: | http://www.sciencedirect.com/science/article/pii/S1738573322003606 |
| _version_ | 1811293192287420416 |
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| author | Sang Ho Kim Jaehyun Ham Byeonghee Lee Sung Il Kim Hwan Yeol Kim Rae-Joon Park Jaehoon Jung |
| author_facet | Sang Ho Kim Jaehyun Ham Byeonghee Lee Sung Il Kim Hwan Yeol Kim Rae-Joon Park Jaehoon Jung |
| author_sort | Sang Ho Kim |
| collection | DOAJ |
| description | The aim of this research is to analyze the characteristics of a core melt discharged from the reactor vessel and the spreading behavior the core melt in the reactor cavity of the SMART. First, a severe accident sequence under conservative conditions is simulated by the MELCOR code to obtain the conditions for an analysis of the spreading behavior and coolability of the ex-vessel melt. Second, the spreading behavior and coolability of the ex-vessel melt are analyzed by the MELTSPREAD code. The level, temperature, and pressure of the water in the cavity as well as the temperature, mass, composition, and discharge velocity of the melt were utilized to construct the ex-vessel analysis. The melt spread only to part of the cavity, and that the height of the corium in a static state was less than 25 cm. The characteristics of a small modular reactor on the spreading behavior and coolability of melt were analyzed. In the SMART, the amount of melt discharged into the cavity is relatively small and the area of the cavity is sufficiently large when compared to a high-power pressurized water reactor. It was found that the coolability of an ex-vessel core melt can be sufficiently secured. |
| first_indexed | 2024-04-13T04:57:54Z |
| format | Article |
| id | doaj.art-379b78f90d334acf9c9a28309d9aebc1 |
| institution | Directory Open Access Journal |
| issn | 1738-5733 |
| language | English |
| last_indexed | 2024-04-13T04:57:54Z |
| publishDate | 2022-12-01 |
| publisher | Elsevier |
| record_format | Article |
| series | Nuclear Engineering and Technology |
| spelling | doaj.art-379b78f90d334acf9c9a28309d9aebc12022-12-22T03:01:26ZengElsevierNuclear Engineering and Technology1738-57332022-12-01541245514559Analysis on the discharge characteristics and spreading behavior of an ex-vessel core melt in the SMARTSang Ho Kim0Jaehyun Ham1Byeonghee Lee2Sung Il Kim3Hwan Yeol Kim4Rae-Joon Park5Jaehoon Jung6Corresponding author. Intelligent Accident Mitigation Research Division, Korea Atomic Energy Research Institute, Daedeok-daero 989Beon-gil 111, Yuseong-gu, Daejeon, 34057, Republic of Korea.; Korea Atomic Energy Research Institute, Daedeok-daero 989Beon-gil 111, Yuseong-gu, Daejeon, 34057, Republic of KoreaKorea Atomic Energy Research Institute, Daedeok-daero 989Beon-gil 111, Yuseong-gu, Daejeon, 34057, Republic of KoreaKorea Atomic Energy Research Institute, Daedeok-daero 989Beon-gil 111, Yuseong-gu, Daejeon, 34057, Republic of KoreaKorea Atomic Energy Research Institute, Daedeok-daero 989Beon-gil 111, Yuseong-gu, Daejeon, 34057, Republic of KoreaKorea Atomic Energy Research Institute, Daedeok-daero 989Beon-gil 111, Yuseong-gu, Daejeon, 34057, Republic of KoreaKorea Atomic Energy Research Institute, Daedeok-daero 989Beon-gil 111, Yuseong-gu, Daejeon, 34057, Republic of KoreaKorea Atomic Energy Research Institute, Daedeok-daero 989Beon-gil 111, Yuseong-gu, Daejeon, 34057, Republic of KoreaThe aim of this research is to analyze the characteristics of a core melt discharged from the reactor vessel and the spreading behavior the core melt in the reactor cavity of the SMART. First, a severe accident sequence under conservative conditions is simulated by the MELCOR code to obtain the conditions for an analysis of the spreading behavior and coolability of the ex-vessel melt. Second, the spreading behavior and coolability of the ex-vessel melt are analyzed by the MELTSPREAD code. The level, temperature, and pressure of the water in the cavity as well as the temperature, mass, composition, and discharge velocity of the melt were utilized to construct the ex-vessel analysis. The melt spread only to part of the cavity, and that the height of the corium in a static state was less than 25 cm. The characteristics of a small modular reactor on the spreading behavior and coolability of melt were analyzed. In the SMART, the amount of melt discharged into the cavity is relatively small and the area of the cavity is sufficiently large when compared to a high-power pressurized water reactor. It was found that the coolability of an ex-vessel core melt can be sufficiently secured.http://www.sciencedirect.com/science/article/pii/S1738573322003606Severe accidentMolten coreCoriumSMARTMELCORMELTSPREAD |
| spellingShingle | Sang Ho Kim Jaehyun Ham Byeonghee Lee Sung Il Kim Hwan Yeol Kim Rae-Joon Park Jaehoon Jung Analysis on the discharge characteristics and spreading behavior of an ex-vessel core melt in the SMART Nuclear Engineering and Technology Severe accident Molten core Corium SMART MELCOR MELTSPREAD |
| title | Analysis on the discharge characteristics and spreading behavior of an ex-vessel core melt in the SMART |
| title_full | Analysis on the discharge characteristics and spreading behavior of an ex-vessel core melt in the SMART |
| title_fullStr | Analysis on the discharge characteristics and spreading behavior of an ex-vessel core melt in the SMART |
| title_full_unstemmed | Analysis on the discharge characteristics and spreading behavior of an ex-vessel core melt in the SMART |
| title_short | Analysis on the discharge characteristics and spreading behavior of an ex-vessel core melt in the SMART |
| title_sort | analysis on the discharge characteristics and spreading behavior of an ex vessel core melt in the smart |
| topic | Severe accident Molten core Corium SMART MELCOR MELTSPREAD |
| url | http://www.sciencedirect.com/science/article/pii/S1738573322003606 |
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