Evaluation of radiation resistance of an austenitic stainless steel with nanosized carbide precipitates using heavy ion irradiation at 200 dpa

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dc.contributor.authorShin, Ji Hoko
dc.contributor.authorKong, Byeong Seoko
dc.contributor.authorJeong, Chaewonko
dc.contributor.authorEom, Hyun Joonko
dc.contributor.authorJang, Changheuiko
dc.contributor.authorShao, Linko
dc.date.accessioned2023-04-03T03:02:35Z-
dc.date.available2023-04-03T03:02:35Z-
dc.date.created2023-04-03-
dc.date.created2023-04-03-
dc.date.issued2023-02-
dc.identifier.citationNUCLEAR ENGINEERING AND TECHNOLOGY, v.55, no.2, pp.555 - 565-
dc.identifier.issn1738-5733-
dc.identifier.urihttp://hdl.handle.net/10203/305946-
dc.description.abstractDespite many advantages as structural materials, austenitic stainless steels (SSs) have been avoided in many next generation nuclear systems due to poor void swelling resistance. In this paper, we report the results of heavy ion irradiation to the recently developed advanced radiation resistant austenitic SS (ARES-6P) with nanosized NbC precipitates. Heavy ion irradiation was performed at high temperatures (500 degrees C and 575 degrees C) to the damage level of-200 displacement per atom (dpa). The measured void swelling of ARES-6P was 2-3%, which was considerably less compared to commercial 316 SS and comparable to ferritic martensitic steels. In addition, increment of hardness measured by nano-indentation was much smaller for ARES-6P compared to 316 SS. Though some nanosized NbC pre-cipitates were dissociated under relatively high dose rate (-5.0 x 10-4 dpa/s), sufficient number of NbC precipitates remained to act as sink sites for the point defects, resulting in such superior radiation resistance.(c) 2022 Korean Nuclear Society, Published by Elsevier Korea LLC. This is an open access article under the CC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/).-
dc.languageEnglish-
dc.publisherKOREAN NUCLEAR SOC-
dc.titleEvaluation of radiation resistance of an austenitic stainless steel with nanosized carbide precipitates using heavy ion irradiation at 200 dpa-
dc.typeArticle-
dc.identifier.wosid000948686500001-
dc.identifier.scopusid2-s2.0-85139877116-
dc.type.rimsART-
dc.citation.volume55-
dc.citation.issue2-
dc.citation.beginningpage555-
dc.citation.endingpage565-
dc.citation.publicationnameNUCLEAR ENGINEERING AND TECHNOLOGY-
dc.identifier.doi10.1016/j.net.2022.09.033-
dc.identifier.kciidART002929720-
dc.contributor.localauthorJang, Changheui-
dc.contributor.nonIdAuthorShao, Lin-
dc.description.isOpenAccessN-
dc.type.journalArticleArticle-
dc.subject.keywordAuthorAdvanced radiation resistant alloy-
dc.subject.keywordAuthorNanosized precipitates-
dc.subject.keywordAuthorAustenitic stainless steel-
dc.subject.keywordAuthorVoid swelling-
dc.subject.keywordAuthorNano indentation-
dc.subject.keywordAuthorHeavy ion irradiation-
dc.subject.keywordPlusMICROSTRUCTURE EVOLUTION-
dc.subject.keywordPlusBEHAVIOR-
dc.subject.keywordPlusINDENTATION-
dc.subject.keywordPlusTEMPERATURE-
dc.subject.keywordPlusDISPERSION-
dc.subject.keywordPlusHARDNESS-
dc.subject.keywordPlusFISSION-
dc.subject.keywordPlusNEUTRON-
dc.subject.keywordPlusALLOYS-
dc.subject.keywordPlusDEFORMATION-
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