Full metadata record
DC Field | Value | Language |
---|---|---|
dc.contributor.author | 김성중 | - |
dc.date.accessioned | 2019-12-08T19:38:14Z | - |
dc.date.available | 2019-12-08T19:38:14Z | - |
dc.date.issued | 2018-08 | - |
dc.identifier.citation | SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS, Article no. 5936214 | en_US |
dc.identifier.issn | 1687-6075 | - |
dc.identifier.issn | 1687-6083 | - |
dc.identifier.uri | https://www.hindawi.com/journals/stni/2018/5936214/ | - |
dc.identifier.uri | https://repository.hanyang.ac.kr/handle/20.500.11754/119748 | - |
dc.description.abstract | 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. | en_US |
dc.description.sponsorship | This work was supported by the National Research Foundation of Korea (NRF) funded by the Ministry of Science & ICT (MSIT, Korea) [Grants nos. NRF-2017M2A8A4018213 and NRF-2017M2B2A9A02049735]. | en_US |
dc.language.iso | en_US | en_US |
dc.publisher | HINDAWI LTD | en_US |
dc.subject | MANAGEMENT | en_US |
dc.title | A Conceptual Approach to Eliminate Bypass Release of Fission Products by In-Containment Relief Valve under SGTR Accident | en_US |
dc.type | Article | en_US |
dc.identifier.doi | 10.1155/2018/5936214 | - |
dc.relation.page | 1-12 | - |
dc.relation.journal | SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS | - |
dc.contributor.googleauthor | Kim, Taeseok | - |
dc.contributor.googleauthor | Choi, Wonjun | - |
dc.contributor.googleauthor | Jeon, Joongoo | - |
dc.contributor.googleauthor | Kim, Nam Kyung | - |
dc.contributor.googleauthor | Jung, Hoichul | - |
dc.contributor.googleauthor | Kim, Sung Joong | - |
dc.relation.code | 2018007344 | - |
dc.sector.campus | S | - |
dc.sector.daehak | COLLEGE OF ENGINEERING[S] | - |
dc.sector.department | DEPARTMENT OF NUCLEAR ENGINEERING | - |
dc.identifier.pid | sungjkim | - |
dc.identifier.researcherID | M-7034-2015 | - |
dc.identifier.orcid | http://orcid.org/0000-0002-8917-6461 | - |
Items in DSpace are protected by copyright, with all rights reserved, unless otherwise indicated.