Thermal Conductivity Evaluation of Compacted Bentonite Buffers Considering Temperature Variations 압축 벤토나이트 완충재의 온도에 따른 열전도도 평가

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dc.contributor.authorYoon, Seokko
dc.contributor.authorPark, Seunghunko
dc.contributor.authorKim, Min-Seopko
dc.contributor.authorKim, Geon-Youngko
dc.contributor.authorLee, Seung-Raeko
dc.date.accessioned2020-10-23T01:56:33Z-
dc.date.available2020-10-23T01:56:33Z-
dc.date.created2020-06-02-
dc.date.created2020-06-02-
dc.date.created2020-06-02-
dc.date.created2020-06-02-
dc.date.issued2020-03-
dc.identifier.citationJournal of Nuclear Fuel Cycle and Waste Technology, v.18, no.1, pp.43 - 49-
dc.identifier.issn1738-1894-
dc.identifier.urihttp://hdl.handle.net/10203/276939-
dc.description.abstractAn engineered barrier system (EBS) for the geological disposal of high-level radioactive waste (HLW) consists of a disposal canister packed with spent fuel, buffer material, backfill material, and gap-filling material. The buffer material fills the space between the canister and the near-field rock, thus serving to restrain the release of radionuclides and protect the canister from groundwater penetration. Furthermore, as significant amounts of heat energy are released from the canister to the surrounding rock, the thermal conductivity of the buffer plays an important role in maintaining the safety of the entire disposal system. Therefore, given the high levels of heat released from disposal canisters, this study measured the thermal conductivities of compacted bentonite buffers from Gyeongju under temperature variations ranging 25 to 80~90℃. There was a 5~20% increase in thermal conductivity as the temperature increased, and the temperature effect increased as the degree of saturation increased.-
dc.languageEnglish-
dc.publisherKorean Radioactive Waste Society-
dc.titleThermal Conductivity Evaluation of Compacted Bentonite Buffers Considering Temperature Variations-
dc.title.alternative압축 벤토나이트 완충재의 온도에 따른 열전도도 평가-
dc.typeArticle-
dc.identifier.scopusid2-s2.0-85084295731-
dc.type.rimsART-
dc.citation.volume18-
dc.citation.issue1-
dc.citation.beginningpage43-
dc.citation.endingpage49-
dc.citation.publicationnameJournal of Nuclear Fuel Cycle and Waste Technology-
dc.identifier.doi10.7733/jnfcwt.2020.18.1.43-
dc.identifier.kciidART002575618-
dc.contributor.localauthorLee, Seung-Rae-
dc.contributor.nonIdAuthorYoon, Seok-
dc.contributor.nonIdAuthorPark, Seunghun-
dc.contributor.nonIdAuthorKim, Geon-Young-
dc.description.isOpenAccessY-
dc.type.journalArticleArticle-
dc.subject.keywordAuthorEngineered barrier system-
dc.subject.keywordAuthorCompacted bentonite buffer-
dc.subject.keywordAuthorThermal conductivity-
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CE-Journal Papers(저널논문)
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