Sensitivity and Uncertainty Analysis for Containment Integrity Using the COFUN Code
DC Field | Value | Language |
---|---|---|
dc.contributor.author | Lim, Dohyun | - |
dc.contributor.author | Jae, Moosung | - |
dc.date.accessioned | 2023-07-05T04:22:06Z | - |
dc.date.available | 2023-07-05T04:22:06Z | - |
dc.date.created | 2023-05-03 | - |
dc.date.issued | 2022-11 | - |
dc.identifier.issn | 0000-0000 | - |
dc.identifier.uri | https://scholarworks.bwise.kr/hanyang/handle/2021.sw.hanyang/186379 | - |
dc.description.abstract | A probabilistic risk assessment (PRA), which is a comprehensive stability assessment tool that includes risks from equipment failures, operator errors, and external environmental factors, is regarded as one of the reliable methods for evaluating the risk from severe accidents of nuclear power plants. A Level 2 PRA models the plant's response to the Level 1 PRA accident sequences that result in reactor core damage. Level 2 PRA for internal event is performed by the COFUN code and source term analysis of severe accidents progression is by the MELCOR code for a reference reactor. As a result of quantification, no containment failure frequency is valued at 70%, large early release frequency (LERF) is 11.1%, and Non-LERF is 18.9%. Through sensitivity analysis, factors affecting the performance and weak parts of the containment are identified. As a result of the sensitivity analysis, sensitivity is found that it was greatly affected by the value of the probability branch value of temperature induced-steam generator tube rupture (TI-SGTR). Finally, uncertainty analysis was performed to confirm the range of the uncertainty band in the result of the point estimate. These results will contribute to the design and safe operation of nuclear power plants. | - |
dc.language | 영어 | - |
dc.language.iso | en | - |
dc.publisher | Institute of Electrical and Electronics Engineers Inc. | - |
dc.title | Sensitivity and Uncertainty Analysis for Containment Integrity Using the COFUN Code | - |
dc.type | Article | - |
dc.contributor.affiliatedAuthor | Jae, Moosung | - |
dc.identifier.doi | 10.1109/ICSRS56243.2022.10067381 | - |
dc.identifier.scopusid | 2-s2.0-85151739841 | - |
dc.identifier.wosid | 000981836500038 | - |
dc.identifier.bibliographicCitation | 2022 6th International Conference on System Reliability and Safety, ICSRS 2022, pp.264 - 269 | - |
dc.relation.isPartOf | 2022 6th International Conference on System Reliability and Safety, ICSRS 2022 | - |
dc.citation.title | 2022 6th International Conference on System Reliability and Safety, ICSRS 2022 | - |
dc.citation.startPage | 264 | - |
dc.citation.endPage | 269 | - |
dc.type.rims | ART | - |
dc.type.docType | Proceedings Paper | - |
dc.description.journalClass | 1 | - |
dc.description.isOpenAccess | N | - |
dc.description.journalRegisteredClass | scopus | - |
dc.relation.journalResearchArea | Engineering | - |
dc.relation.journalWebOfScienceCategory | Engineering, Multidisciplinary | - |
dc.subject.keywordPlus | Codes (symbols) | - |
dc.subject.keywordPlus | Nuclear energy | - |
dc.subject.keywordPlus | Nuclear fuels | - |
dc.subject.keywordPlus | Nuclear reactor accidents | - |
dc.subject.keywordPlus | Risk assessment | - |
dc.subject.keywordPlus | Sensitivity analysis | - |
dc.subject.keywordPlus | Steam generators | - |
dc.subject.keywordPlus | System stability | - |
dc.subject.keywordPlus | Uncertainty analysis | - |
dc.subject.keywordPlus | Assessment tool | - |
dc.subject.keywordPlus | Containment integrity | - |
dc.subject.keywordPlus | Internal event | - |
dc.subject.keywordPlus | Larger early release frequencies | - |
dc.subject.keywordPlus | Level 2 | - |
dc.subject.keywordPlus | Level 2 probabilistic risk assessment | - |
dc.subject.keywordPlus | Probabilistic Risk Assessment | - |
dc.subject.keywordPlus | Sensitivity and uncertainty analysis | - |
dc.subject.keywordPlus | Severe accident | - |
dc.subject.keywordPlus | Stability assessment | - |
dc.subject.keywordPlus | Nuclear power plants | - |
dc.subject.keywordAuthor | containment integrity | - |
dc.subject.keywordAuthor | internal event | - |
dc.subject.keywordAuthor | level 2 probabilistic risk assessment | - |
dc.identifier.url | https://ieeexplore.ieee.org/document/10067381 | - |
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