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김희령

Kim, Hee Reyoung
RAdiation and MagnetohydroDynamics Advanced Lab.
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DC Field Value Language
dc.citation.endPage 1945 -
dc.citation.number 5 -
dc.citation.startPage 1935 -
dc.citation.title NUCLEAR ENGINEERING AND TECHNOLOGY -
dc.citation.volume 55 -
dc.contributor.author Byun, Jaehoon -
dc.contributor.author Yoon, Seungbin -
dc.contributor.author Kim, Hee Reyoung -
dc.date.accessioned 2023-12-21T12:40:59Z -
dc.date.available 2023-12-21T12:40:59Z -
dc.date.created 2022-12-07 -
dc.date.issued 2023-05 -
dc.description.abstract The radiological safety of workers in a newly developed microwave-based spent resin treatment facility was assessed based on work location and operational scenarios. The results show that the remote-operation room worker was exposed to maximum annual dose of 3.19E+00 mSv, which is 15.9% of the dose limit, thereby confirming radiological safety. Inside the pathway, annual doses in the range of 7.87E-02–2.07E-01 mSv were measured initially at the mock-up tank and later at the point between the spent resin separation and treatment parts. The dose of emergency maintenance workers was below the dose limit (4.08E-03–4.99E+00 mSv); however, before treatment (separation and microwave), the dose of maintenance and repair workers exceeded the dose limit. The doses of the effluent removal workers at the zeolite and activated carbon storage tank and spent resin storage tank were the lowest at 2.79E-01–2.87E-01 mSv and 9.27E-01 mSv in “1 h” and “4–5 h of operation”, respectively. The immediately lower and upper layers of the facility room exhibited the highest annual doses of 1.84E+00 and 3.22E+00 mSv, respectively. Through this study, a scenario that can minimize the dose considering the movement of spent resin through the facility can be developed. -
dc.identifier.bibliographicCitation NUCLEAR ENGINEERING AND TECHNOLOGY, v.55, no.5, pp.1935 - 1945 -
dc.identifier.doi 10.1016/j.net.2022.12.006 -
dc.identifier.issn 1738-5733 -
dc.identifier.scopusid 2-s2.0-85144851150 -
dc.identifier.uri https://scholarworks.unist.ac.kr/handle/201301/60079 -
dc.identifier.url https://www.sciencedirect.com/science/article/pii/S1738573322005733?via%3Dihub -
dc.identifier.wosid 001002457900001 -
dc.language 영어 -
dc.publisher 한국원자력학회 -
dc.title Radiological safety analysis of a newly designed spent resin mixture treatment facility during normal and abnormal operational scenarios for the safety of radiation workers -
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 Exposure scenarios -
dc.subject.keywordAuthor Spent resin treatment -
dc.subject.keywordAuthor VISIPLAN -
dc.subject.keywordAuthor Dose evaluation -
dc.subject.keywordAuthor Exposure dose -

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