Full metadata record
DC Field | Value | Language |
---|---|---|
dc.citation.endPage | 448 | - |
dc.citation.number | 2 | - |
dc.citation.startPage | 442 | - |
dc.citation.title | NUCLEAR ENGINEERING AND TECHNOLOGY | - |
dc.citation.volume | 54 | - |
dc.contributor.author | Choi, Woo Nyun | - |
dc.contributor.author | Byun, Jaehoon | - |
dc.contributor.author | Kim, Hee Reyoung | - |
dc.date.accessioned | 2023-12-21T14:38:52Z | - |
dc.date.available | 2023-12-21T14:38:52Z | - |
dc.date.created | 2022-02-03 | - |
dc.date.issued | 2022-02 | - |
dc.description.abstract | Intermediate-level radioactive waste (ILW) is not subject to legal approval for cave disposal in Korea. To solve this problem, a spent resin treatment device that separates 14C-containing resin from zeolite/activated carbon and desorbs 14C through a microwave device has been developed. In this study, we evaluated the radiological safety of the operators performing repair work in the event of a failure in such a device treating 1 ton of spent resin mixture per day. Based on the safety evaluation results, it is possible to formulate a design plan that can ensure the safety of workers while developing a commercialized device. When each component of the resin treatment device can be repaired from the outside, the maximum and minimum allowable repair times are calculated as 263.2 h and 27.7 h for the 14C-detached resin storage tank and zeolite/activated carbon storage tank, respectively. For at least 6 h per quarter, the worker's annual dose limit remains within 50 mSv/year; further, over 5 years, it remained within 100 mSv. At least 6 h of repair time per quarter is considered, under conservative conditions, to verify the radiological safety of the worker during repair work within that time. © 2021 Korean Nuclear Society | - |
dc.identifier.bibliographicCitation | NUCLEAR ENGINEERING AND TECHNOLOGY, v.54, no.2, pp.442 - 448 | - |
dc.identifier.doi | 10.1016/j.net.2021.06.015 | - |
dc.identifier.issn | 1738-5733 | - |
dc.identifier.scopusid | 2-s2.0-85108979570 | - |
dc.identifier.uri | https://scholarworks.unist.ac.kr/handle/201301/57158 | - |
dc.identifier.url | https://www.sciencedirect.com/science/article/pii/S1738573321003363?via%3Dihub | - |
dc.identifier.wosid | 000753340300004 | - |
dc.language | 영어 | - |
dc.publisher | KOREAN NUCLEAR SOC | - |
dc.title | Evaluation of dose received by workers while repairing a failed spent resin mixture treatment device | - |
dc.type | Article | - |
dc.description.isOpenAccess | TRUE | - |
dc.relation.journalWebOfScienceCategory | Nuclear Science & Technology | - |
dc.relation.journalResearchArea | Nuclear Science & Technology | - |
dc.type.docType | Article | - |
dc.description.journalRegisteredClass | scie | - |
dc.description.journalRegisteredClass | scopus | - |
dc.description.journalRegisteredClass | kci | - |
dc.subject.keywordAuthor | Ion-exchange resin | - |
dc.subject.keywordAuthor | Nuclear power plant | - |
dc.subject.keywordAuthor | Radioactive waste | - |
dc.subject.keywordAuthor | Radiological safety | - |
dc.subject.keywordAuthor | Repair work | - |
dc.subject.keywordAuthor | Spent resin treatment device | - |
dc.subject.keywordPlus | REACTORS | - |
dc.subject.keywordPlus | WATER | - |
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