A Conceptual Approach to Eliminate Bypass Release of Fission Products by In-Containment Relief Valve under SGTR Accident
During a hypothesized severe accident, a containment building is designed to act as a final barrier to prevent release of fission products to the environment in nuclear power plants. However, in a bypass scenario of steam generator tube rupture (SGTR), radioactive nuclides can be released to environ...
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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/10.1155/2018/5936214 |
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| author | Taeseok Kim Wonjun Choi Joongoo Jeon Nam Kyung Kim Hoichul Jung Sung Joong Kim |
| author_facet | Taeseok Kim Wonjun Choi Joongoo Jeon Nam Kyung Kim Hoichul Jung Sung Joong Kim |
| author_sort | Taeseok Kim |
| collection | DOAJ |
| description | During a hypothesized severe accident, a containment building is designed to act as a final barrier to prevent release of fission products to the environment in nuclear power plants. However, in a bypass scenario of steam generator tube rupture (SGTR), radioactive nuclides can be released to environment even if the containment is not ruptured. Thus, thorough mitigation strategies are needed to prevent such unfiltered release of the radioactive nuclides during SGTR accidents. To mitigate the consequence of the SGTR accident, this study was conducted to devise a conceptual approach of installing In-Containment Relief Valve (ICRV) from steam generator (SG) to the free space in the containment building and it was simulated by MELCOR code for numerical analysis. Simulation results show that the radioactive nuclides were not released to the environment in the ICRV case. However, the containment pressure increased more than the base case, which is a disadvantage of the ICRV. To minimize the negative effects of the ICRV, the ICRV linked to Reactor Drain Tank (RDT) and cavity flooding was performed. Because the overpressurization of containment is due to heat of ex-vessel corium, only cavity flooding was effective for depressurization. The conceptual design of the ICRV is effective in mitigating the SGTR accident. |
| format | Article |
| id | doaj-art-53a2869961284324adb8cda000c37eb0 |
| 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-53a2869961284324adb8cda000c37eb02025-02-03T01:13:00ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832018-01-01201810.1155/2018/59362145936214A Conceptual Approach to Eliminate Bypass Release of Fission Products by In-Containment Relief Valve under SGTR AccidentTaeseok Kim0Wonjun Choi1Joongoo Jeon2Nam Kyung Kim3Hoichul Jung4Sung Joong Kim5Department of Nuclear Engineering, Hanyang University, Seoul 04763, Republic of KoreaDepartment of Nuclear Engineering, Hanyang University, Seoul 04763, Republic of KoreaDepartment of Nuclear Engineering, Hanyang University, Seoul 04763, Republic of KoreaDepartment of Nuclear Engineering, Hanyang University, Seoul 04763, Republic of KoreaDepartment of Nuclear Engineering, Hanyang University, Seoul 04763, Republic of KoreaDepartment of Nuclear Engineering, Hanyang University, Seoul 04763, Republic of KoreaDuring a hypothesized severe accident, a containment building is designed to act as a final barrier to prevent release of fission products to the environment in nuclear power plants. However, in a bypass scenario of steam generator tube rupture (SGTR), radioactive nuclides can be released to environment even if the containment is not ruptured. Thus, thorough mitigation strategies are needed to prevent such unfiltered release of the radioactive nuclides during SGTR accidents. To mitigate the consequence of the SGTR accident, this study was conducted to devise a conceptual approach of installing In-Containment Relief Valve (ICRV) from steam generator (SG) to the free space in the containment building and it was simulated by MELCOR code for numerical analysis. Simulation results show that the radioactive nuclides were not released to the environment in the ICRV case. However, the containment pressure increased more than the base case, which is a disadvantage of the ICRV. To minimize the negative effects of the ICRV, the ICRV linked to Reactor Drain Tank (RDT) and cavity flooding was performed. Because the overpressurization of containment is due to heat of ex-vessel corium, only cavity flooding was effective for depressurization. The conceptual design of the ICRV is effective in mitigating the SGTR accident.http://dx.doi.org/10.1155/2018/5936214 |
| spellingShingle | Taeseok Kim Wonjun Choi Joongoo Jeon Nam Kyung Kim Hoichul Jung Sung Joong Kim A Conceptual Approach to Eliminate Bypass Release of Fission Products by In-Containment Relief Valve under SGTR Accident Science and Technology of Nuclear Installations |
| title | A Conceptual Approach to Eliminate Bypass Release of Fission Products by In-Containment Relief Valve under SGTR Accident |
| title_full | A Conceptual Approach to Eliminate Bypass Release of Fission Products by In-Containment Relief Valve under SGTR Accident |
| title_fullStr | A Conceptual Approach to Eliminate Bypass Release of Fission Products by In-Containment Relief Valve under SGTR Accident |
| title_full_unstemmed | A Conceptual Approach to Eliminate Bypass Release of Fission Products by In-Containment Relief Valve under SGTR Accident |
| title_short | A Conceptual Approach to Eliminate Bypass Release of Fission Products by In-Containment Relief Valve under SGTR Accident |
| title_sort | conceptual approach to eliminate bypass release of fission products by in containment relief valve under sgtr accident |
| url | http://dx.doi.org/10.1155/2018/5936214 |
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