A study on DCGL determination and the classification of contaminated areas for preliminary decommission planning of KEPCO-NF nuclear fuel fabrication facility
DC Field | Value | Language |
---|---|---|
dc.contributor.author | Cho, Seo-Yeon | - |
dc.contributor.author | Kim, Yong-Soo | - |
dc.contributor.author | Park, Da-Won | - |
dc.contributor.author | Park, Chan-Jun | - |
dc.date.accessioned | 2021-08-02T10:28:05Z | - |
dc.date.available | 2021-08-02T10:28:05Z | - |
dc.date.created | 2021-05-12 | - |
dc.date.issued | 2019-12 | - |
dc.identifier.issn | 1738-5733 | - |
dc.identifier.uri | https://scholarworks.bwise.kr/hanyang/handle/2021.sw.hanyang/11615 | - |
dc.description.abstract | As a part of the preliminary decommissioning plan of KEPCO-NF fuel fabrication facility, DCGLs of three target radionuclides, 234U, 235U, and 238U, were derived using RESRAD-BUILD code and contaminated areas of the facility were classified based on contamination levels from the derived DCGLs. From code simulations, one-room modeling results showed that the grinding room in building #2 was the most restrictive (DCGLgross = 10493.01 Bq/m2). The DCGLgross results in contaminated areas from one-room modeling were slightly more conservative than three-room modeling. Prior to the code simulation, field survey and measurements conducted by each survey unit. For a conservative approach, the most restrictive DCGLgross in each survey unit was taken as a reference to classify the contaminated areas of the facility. Accordingly, seven rooms and 37 rooms in the nuclear-fuel buildings were classified as Class 1 and Class 2, respectively. As expected, fuel material handling and processing rooms such as the grinding room, sintering room, compressing room, and powder collecting room were included in the Class 1 area. | - |
dc.language | 영어 | - |
dc.language.iso | en | - |
dc.publisher | KOREAN NUCLEAR SOC | - |
dc.title | A study on DCGL determination and the classification of contaminated areas for preliminary decommission planning of KEPCO-NF nuclear fuel fabrication facility | - |
dc.type | Article | - |
dc.contributor.affiliatedAuthor | Kim, Yong-Soo | - |
dc.identifier.doi | 10.1016/j.net.2019.06.012 | - |
dc.identifier.scopusid | 2-s2.0-85076566207 | - |
dc.identifier.wosid | 000503184600007 | - |
dc.identifier.bibliographicCitation | NUCLEAR ENGINEERING AND TECHNOLOGY, v.51, no.8, pp.1951 - 1956 | - |
dc.relation.isPartOf | NUCLEAR ENGINEERING AND TECHNOLOGY | - |
dc.citation.title | NUCLEAR ENGINEERING AND TECHNOLOGY | - |
dc.citation.volume | 51 | - |
dc.citation.number | 8 | - |
dc.citation.startPage | 1951 | - |
dc.citation.endPage | 1956 | - |
dc.type.rims | ART | - |
dc.type.docType | Article | - |
dc.identifier.kciid | ART002530184 | - |
dc.description.journalClass | 1 | - |
dc.description.isOpenAccess | Y | - |
dc.description.journalRegisteredClass | scie | - |
dc.description.journalRegisteredClass | scopus | - |
dc.description.journalRegisteredClass | kci | - |
dc.relation.journalResearchArea | Nuclear Science & Technology | - |
dc.relation.journalWebOfScienceCategory | Nuclear Science & Technology | - |
dc.subject.keywordPlus | KOREA | - |
dc.subject.keywordAuthor | DCGL | - |
dc.subject.keywordAuthor | Decommissioning | - |
dc.subject.keywordAuthor | Nuclear fuel fabrication facility | - |
dc.subject.keywordAuthor | RESRAD-BUILD | - |
dc.subject.keywordAuthor | MARSSIM | - |
dc.identifier.url | https://www.sciencedirect.com/science/article/pii/S1738573319301639?via%3Dihub | - |
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