Analysis of Steam Generator Tube Rupture Accidents for the Development of Mitigation Strategies
DC Field | Value | Language |
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dc.contributor.author | Bang, Jungjin | - |
dc.contributor.author | Choi, Gi Hyeon | - |
dc.contributor.author | Jerng, Dong-Wook | - |
dc.contributor.author | Bae, Sung-Won | - |
dc.contributor.author | Jang, Sunghyon | - |
dc.contributor.author | Ha, Sang Jun | - |
dc.date.accessioned | 2022-02-07T02:42:09Z | - |
dc.date.available | 2022-02-07T02:42:09Z | - |
dc.date.issued | 2022-01 | - |
dc.identifier.issn | 1738-5733 | - |
dc.identifier.uri | https://scholarworks.bwise.kr/cau/handle/2019.sw.cau/54858 | - |
dc.description.abstract | We analyzed mitigation strategies for steam generator tube rupture (SGTR) accidents using MARS code under both full-power and low-power and shutdown (LPSD) conditions. In general, there are two approaches to mitigating SGTR accidents: supplementing the reactor coolant inventory using safety injection systems and depressurizing the reactor coolant system (RCS) by cooling it down using the intact steam generator. These mitigation strategies were compared from the viewpoint of break flow from the ruptured steam generator tube, the core integrity, and the possibility of the main steam safety valves opening, which is associated with the potential release of radiation. The “cooldown strategy” is recommended for break flow control, whereas the “RCS make-up strategy” is better for RCS inventory control. Under full power, neither mitigation strategy made a significant difference except for on the break flow while, in LPSD modes, the RCS cooldown strategy resulted in lower break and discharge flows, and thus less radiation release. As a result, using the cooldown strategy for an SGTR under LPSD conditions is recommended. These results can be used as a fundamental guide for mitigation strategies for SGTR accidents according to the operational mode. | - |
dc.format.extent | 10 | - |
dc.language | 영어 | - |
dc.language.iso | ENG | - |
dc.publisher | 한국원자력학회 | - |
dc.title | Analysis of Steam Generator Tube Rupture Accidents for the Development of Mitigation Strategies | - |
dc.title.alternative | Analysis of Steam Generator Tube Rupture Accidents for the Development of Mitigation Strategies | - |
dc.type | Article | - |
dc.identifier.doi | 10.1016/j.net.2021.07.032 | - |
dc.identifier.bibliographicCitation | Nuclear Engineering and Technology, v.54, no.1, pp 152 - 161 | - |
dc.identifier.kciid | ART002803603 | - |
dc.description.isOpenAccess | N | - |
dc.identifier.wosid | 000745917800003 | - |
dc.citation.endPage | 161 | - |
dc.citation.number | 1 | - |
dc.citation.startPage | 152 | - |
dc.citation.title | Nuclear Engineering and Technology | - |
dc.citation.volume | 54 | - |
dc.type.docType | Article | - |
dc.publisher.location | 대한민국 | - |
dc.subject.keywordAuthor | Steam generator | - |
dc.subject.keywordAuthor | SGTR | - |
dc.subject.keywordAuthor | Mitigation strategy | - |
dc.subject.keywordAuthor | Operational mode | - |
dc.subject.keywordAuthor | Accident management | - |
dc.subject.keywordAuthor | PWR type reactor | - |
dc.relation.journalResearchArea | Nuclear Science & Technology | - |
dc.relation.journalWebOfScienceCategory | Nuclear Science & Technology | - |
dc.description.journalRegisteredClass | scie | - |
dc.description.journalRegisteredClass | scopus | - |
dc.description.journalRegisteredClass | kci | - |
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