Source Term Estimation under the SBLOCA-Induced Severe Accident Condition in the SMART
The SMART is a system-integrated modular reactor in which a nuclear steam supply system with a thermal power of 365 MW is contained inside of the reactor vessel. Although the probability is very low, the reactor core can be damaged during a small break loss-of-coolant accident when both the passive...
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| Format: | Article |
| Language: | English |
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Wiley
2021-01-01
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| Series: | Science and Technology of Nuclear Installations |
| Online Access: | http://dx.doi.org/10.1155/2021/6686615 |
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| author | Jaehyun Ham Sang Ho Kim Sung Il Kim Byeonghee Lee Jong-Hwa Park Rae-Joon Park Jaehoon Jung |
| author_facet | Jaehyun Ham Sang Ho Kim Sung Il Kim Byeonghee Lee Jong-Hwa Park Rae-Joon Park Jaehoon Jung |
| author_sort | Jaehyun Ham |
| collection | DOAJ |
| description | The SMART is a system-integrated modular reactor in which a nuclear steam supply system with a thermal power of 365 MW is contained inside of the reactor vessel. Although the probability is very low, the reactor core can be damaged during a small break loss-of-coolant accident when both the passive safety injection system and the passive residual heat removal system are completely unavailable. In this work, a total of five cases were analyzed considering the reactor vessel condition and the availability of the radioactivity removal tanks and the ancillary containment spray system as containment condition variables using MELCOR code. It was estimated that there is no containment failure based on pressure, hydrogen mole fraction, and ablation depth, so that the release fractions of the 12 classes of fission products in MELCOR were evaluated considering design leak only for all cases. The overall source term of the case in which the integrity of the reactor vessel is maintained by the early initiation of the cavity flooding system was similar to that of the reactor vessel failure case. While the release fraction of cesium to the environment was analyzed to increase when there is no water in the radioactivity removal tanks, the fraction is small enough at which the radioactivity of the released cesium-137 remains well below 100 TBq, a regulatory limit. Moreover, it was found that the source term can be cut in half if the ancillary containment spray system is available. The results of this study verify the safety performance of the SMART under the small break loss-of-coolant severe accident condition with respect to the source term of interest. |
| format | Article |
| id | doaj-art-c152b8ee1f704d8d868dabceac9df99e |
| institution | OA Journals |
| issn | 1687-6075 1687-6083 |
| language | English |
| publishDate | 2021-01-01 |
| publisher | Wiley |
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| series | Science and Technology of Nuclear Installations |
| spelling | doaj-art-c152b8ee1f704d8d868dabceac9df99e2025-08-20T02:19:14ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832021-01-01202110.1155/2021/66866156686615Source Term Estimation under the SBLOCA-Induced Severe Accident Condition in the SMARTJaehyun Ham0Sang Ho Kim1Sung Il Kim2Byeonghee Lee3Jong-Hwa Park4Rae-Joon Park5Jaehoon Jung6Korea Atomic Energy Research Institute, 1045 Daedeok-daero, Yuseong-Gu, Daejeon 34039, Republic of KoreaKorea Atomic Energy Research Institute, 1045 Daedeok-daero, Yuseong-Gu, Daejeon 34039, Republic of KoreaKorea Atomic Energy Research Institute, 1045 Daedeok-daero, Yuseong-Gu, Daejeon 34039, Republic of KoreaKorea Atomic Energy Research Institute, 1045 Daedeok-daero, Yuseong-Gu, Daejeon 34039, Republic of KoreaKorea Atomic Energy Research Institute, 1045 Daedeok-daero, Yuseong-Gu, Daejeon 34039, Republic of KoreaKorea Atomic Energy Research Institute, 1045 Daedeok-daero, Yuseong-Gu, Daejeon 34039, Republic of KoreaKorea Atomic Energy Research Institute, 1045 Daedeok-daero, Yuseong-Gu, Daejeon 34039, Republic of KoreaThe SMART is a system-integrated modular reactor in which a nuclear steam supply system with a thermal power of 365 MW is contained inside of the reactor vessel. Although the probability is very low, the reactor core can be damaged during a small break loss-of-coolant accident when both the passive safety injection system and the passive residual heat removal system are completely unavailable. In this work, a total of five cases were analyzed considering the reactor vessel condition and the availability of the radioactivity removal tanks and the ancillary containment spray system as containment condition variables using MELCOR code. It was estimated that there is no containment failure based on pressure, hydrogen mole fraction, and ablation depth, so that the release fractions of the 12 classes of fission products in MELCOR were evaluated considering design leak only for all cases. The overall source term of the case in which the integrity of the reactor vessel is maintained by the early initiation of the cavity flooding system was similar to that of the reactor vessel failure case. While the release fraction of cesium to the environment was analyzed to increase when there is no water in the radioactivity removal tanks, the fraction is small enough at which the radioactivity of the released cesium-137 remains well below 100 TBq, a regulatory limit. Moreover, it was found that the source term can be cut in half if the ancillary containment spray system is available. The results of this study verify the safety performance of the SMART under the small break loss-of-coolant severe accident condition with respect to the source term of interest.http://dx.doi.org/10.1155/2021/6686615 |
| spellingShingle | Jaehyun Ham Sang Ho Kim Sung Il Kim Byeonghee Lee Jong-Hwa Park Rae-Joon Park Jaehoon Jung Source Term Estimation under the SBLOCA-Induced Severe Accident Condition in the SMART Science and Technology of Nuclear Installations |
| title | Source Term Estimation under the SBLOCA-Induced Severe Accident Condition in the SMART |
| title_full | Source Term Estimation under the SBLOCA-Induced Severe Accident Condition in the SMART |
| title_fullStr | Source Term Estimation under the SBLOCA-Induced Severe Accident Condition in the SMART |
| title_full_unstemmed | Source Term Estimation under the SBLOCA-Induced Severe Accident Condition in the SMART |
| title_short | Source Term Estimation under the SBLOCA-Induced Severe Accident Condition in the SMART |
| title_sort | source term estimation under the sbloca induced severe accident condition in the smart |
| url | http://dx.doi.org/10.1155/2021/6686615 |
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