Sensitivity Analysis of RCS Depressurization Strategy Under a Postulated SGTR Accident in OPR1000
DC Field | Value | Language |
---|---|---|
dc.contributor.author | Choi, Wonjun | - |
dc.contributor.author | Kim, Taeseok | - |
dc.contributor.author | Jeon, Joongoo | - |
dc.contributor.author | Kim, Nam Kyung | - |
dc.contributor.author | Kim, Sung Joong | - |
dc.date.accessioned | 2021-08-02T13:27:06Z | - |
dc.date.available | 2021-08-02T13:27:06Z | - |
dc.date.created | 2021-05-14 | - |
dc.date.issued | 2018-07 | - |
dc.identifier.uri | https://scholarworks.bwise.kr/hanyang/handle/2021.sw.hanyang/16801 | - |
dc.description.abstract | Steam generator tube rupture (SGTR) accident is one of important accident that has high probability of resulting in severe accidents. As a bypass scenario, fission product can be directly released to the environment during the SGTR accident. Thus, the severe accident by SGTR should be carefully managed by severe accident management guidance (SAMG). In Korea, SAMG for optimized power reactor 1000 (OPR1000) has been developed in 1999 and used to mitigate the severe accident of OPR1000 with seven mitigation strategies. Among the mitigation strategies, ‘Depressurization of reactor coolant system (RCS)’ is one of the most powerful strategies to reduce direct release of the fission product. To reduce the RCS pressure, indirect depressurization using steam generator is generally recommended. However, depending on the RCS condition, the indirect depressurization can be ineffective to reduce the RCS pressure. In this case, direct depressurization using pilot operated relief valve (PORV) should be performed as a second plan. From this point of view, sensitivity study of RCS depressurization was performed to investigate priority of depressurization in this study. The severe accident scenario initiated by SGTR accident was selected from probabilistic safety assessment (PSA) level 1 report and simulated using MELCOR 2.1. For the mitigation strategy, various timing of depressurization, the number of opening valves and flow rate of feed water were applied to simulate the possible depressurization strategies during the severe accident. The MELCOR code simulation shows that if depressurization was performed at 30 minutes after SAMG entrance, the direct depressurization was more efficient to reduce the RCS pressure and the fission product release. Therefore, it was recommended to use direct depressurization rather than indirect depressurization in certain time. The sensitivity of flow rate of feed water and different number of opening valves were insignificant for progress of the accident and fission product release. In conclusion, operators should select the way of depressurization to reduce the RCS pressure and the fission product release during the SGTR accident, considering the condition of the plant such as accident progress and availability of safety features. To suggest more proper information for depressurization, more sensitivity analysis and detailed thermal-hydraulic analysis should be performed for the future work. | - |
dc.language | 영어 | - |
dc.language.iso | en | - |
dc.publisher | The American Society of Mechanical Engineers | - |
dc.title | Sensitivity Analysis of RCS Depressurization Strategy Under a Postulated SGTR Accident in OPR1000 | - |
dc.type | Article | - |
dc.contributor.affiliatedAuthor | Kim, Sung Joong | - |
dc.identifier.doi | 10.1115/ICONE26-82074 | - |
dc.identifier.bibliographicCitation | Proceedings of the 26th International Conference on Nuclear Engineering, pp.1 - 6 | - |
dc.relation.isPartOf | Proceedings of the 26th International Conference on Nuclear Engineering | - |
dc.citation.title | Proceedings of the 26th International Conference on Nuclear Engineering | - |
dc.citation.startPage | 1 | - |
dc.citation.endPage | 6 | - |
dc.type.rims | ART | - |
dc.type.docType | Proceeding | - |
dc.description.journalClass | 1 | - |
dc.description.isOpenAccess | N | - |
dc.description.journalRegisteredClass | other | - |
dc.subject.keywordAuthor | Accidents | - |
dc.subject.keywordAuthor | Sensitivity analysis | - |
dc.subject.keywordAuthor | Nuclear fission | - |
dc.subject.keywordAuthor | Pressure | - |
dc.subject.keywordAuthor | Boilers | - |
dc.subject.keywordAuthor | Feedwater | - |
dc.subject.keywordAuthor | Flow (Dynamics) | - |
dc.subject.keywordAuthor | Valves | - |
dc.subject.keywordAuthor | Accident management | - |
dc.subject.keywordAuthor | Nuclear reactor coolants | - |
dc.subject.keywordAuthor | Probabilistic safety assessment | - |
dc.subject.keywordAuthor | Probability | - |
dc.subject.keywordAuthor | Relief valves | - |
dc.subject.keywordAuthor | Rupture | - |
dc.subject.keywordAuthor | Safety | - |
dc.subject.keywordAuthor | Simulation | - |
dc.identifier.url | https://asmedigitalcollection.asme.org/ICONE/proceedings-abstract/ICONE26/51517/V007T11A011/273353 | - |
Items in ScholarWorks are protected by copyright, with all rights reserved, unless otherwise indicated.
222, Wangsimni-ro, Seongdong-gu, Seoul, 04763, Korea+82-2-2220-1365
COPYRIGHT © 2021 HANYANG UNIVERSITY.
Certain data included herein are derived from the © Web of Science of Clarivate Analytics. All rights reserved.
You may not copy or re-distribute this material in whole or in part without the prior written consent of Clarivate Analytics.