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College of Engineering(공과대학)Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)NE-Journal Papers(저널논문)

Development of alumina-forming duplex stainless steels as accident-tolerant fuel cladding materials for light water reactors

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dc.contributor.authorKim, Hyunmyungko
dc.contributor.authorJang, Hunko
dc.contributor.authorSubramanian, Gokul Obulanko
dc.contributor.authorKim, Chaewonko
dc.contributor.authorJang, Changheuiko
dc.date.accessioned2018-08-20T07:47:15Z-
dc.date.available2018-08-20T07:47:15Z-
dc.date.created2018-08-01-
dc.date.created2018-08-01-
dc.date.created2018-08-01-
dc.date.created2018-08-01-
dc.date.issued2018-08-
dc.identifier.citationJOURNAL OF NUCLEAR MATERIALS, v.507, pp.1 - 14-
dc.identifier.issn0022-3115-
dc.identifier.urihttp://hdl.handle.net/10203/244818-
dc.description.abstractHigh aluminum content (>5 wt.%) duplex stainless steels were developed as accident-tolerant fuel (ATF) cladding materials for light water reactors. A set of model alumina-forming duplex stainless steel (ADSS) alloys with a nominal composition range of Fe-(18-21)Ni-(16-21)Cr-(5-6)Al were prepared and tested for corrosion resistance in both 1200 degrees C steam and simulated pressurized water reactor (PWR) operating conditions. The performance and properties of the ADSS alloys were compared to those of the austenitic (310 S) and ferritic (FeCrAI-APM) stainless steels. The results showed that the ADSS alloys possessed good corrosion resistances in both conditions, and better tensile properties. The applicability of the ADSS alloys as ATF cladding materials was discussed in view of their corrosion resistance, irradiation resistance, and embrittlement. (C) 2018 Elsevier B.V. All rights reserved.-
dc.languageEnglish-
dc.publisherELSEVIER SCIENCE BV-
dc.titleDevelopment of alumina-forming duplex stainless steels as accident-tolerant fuel cladding materials for light water reactors-
dc.typeArticle-
dc.identifier.wosid000438019800001-
dc.identifier.scopusid2-s2.0-85046012966-
dc.type.rimsART-
dc.citation.volume507-
dc.citation.beginningpage1-
dc.citation.endingpage14-
dc.citation.publicationnameJOURNAL OF NUCLEAR MATERIALS-
dc.identifier.doi10.1016/j.jnucmat.2018.04.027-
dc.contributor.localauthorJang, Changheui-
dc.contributor.nonIdAuthorJang, Hun-
dc.contributor.nonIdAuthorKim, Chaewon-
dc.description.isOpenAccessN-
dc.type.journalArticleArticle-
dc.subject.keywordAuthorAccident-tolerant fuel cladding-
dc.subject.keywordAuthorAlumina-forming duplex stainless steel-
dc.subject.keywordAuthorHigh-temperature steam oxidation-
dc.subject.keywordAuthorPWR autoclave corrosion-
dc.subject.keywordAuthorTensile strength-
dc.subject.keywordPlusCORROSION BEHAVIOR-
dc.subject.keywordPlusMECHANICAL-PROPERTIES-
dc.subject.keywordPlusHEAT-TREATMENT-
dc.subject.keywordPlusFECRAL ALLOYS-
dc.subject.keywordPlusPRECIPITATION-
dc.subject.keywordPlusEMBRITTLEMENT-
dc.subject.keywordPlusTEMPERATURE-
dc.subject.keywordPlusMICROSTRUCTURE-
dc.subject.keywordPlusENVIRONMENTS-
dc.subject.keywordPlusDUCTILITY-
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