DC Field | Value | Language |
---|---|---|
dc.contributor.author | Shin, Ji Ho | ko |
dc.contributor.author | Kong, Byeong Seo | ko |
dc.contributor.author | Jeong, Chaewon | ko |
dc.contributor.author | Eom, Hyun Joon | ko |
dc.contributor.author | Jang, Changheui | ko |
dc.contributor.author | Shao, Lin | ko |
dc.date.accessioned | 2023-04-03T03:02:35Z | - |
dc.date.available | 2023-04-03T03:02:35Z | - |
dc.date.created | 2023-04-03 | - |
dc.date.created | 2023-04-03 | - |
dc.date.issued | 2023-02 | - |
dc.identifier.citation | NUCLEAR ENGINEERING AND TECHNOLOGY, v.55, no.2, pp.555 - 565 | - |
dc.identifier.issn | 1738-5733 | - |
dc.identifier.uri | http://hdl.handle.net/10203/305946 | - |
dc.description.abstract | Despite 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.language | English | - |
dc.publisher | KOREAN NUCLEAR SOC | - |
dc.title | Evaluation of radiation resistance of an austenitic stainless steel with nanosized carbide precipitates using heavy ion irradiation at 200 dpa | - |
dc.type | Article | - |
dc.identifier.wosid | 000948686500001 | - |
dc.identifier.scopusid | 2-s2.0-85139877116 | - |
dc.type.rims | ART | - |
dc.citation.volume | 55 | - |
dc.citation.issue | 2 | - |
dc.citation.beginningpage | 555 | - |
dc.citation.endingpage | 565 | - |
dc.citation.publicationname | NUCLEAR ENGINEERING AND TECHNOLOGY | - |
dc.identifier.doi | 10.1016/j.net.2022.09.033 | - |
dc.identifier.kciid | ART002929720 | - |
dc.contributor.localauthor | Jang, Changheui | - |
dc.contributor.nonIdAuthor | Shao, Lin | - |
dc.description.isOpenAccess | N | - |
dc.type.journalArticle | Article | - |
dc.subject.keywordAuthor | Advanced radiation resistant alloy | - |
dc.subject.keywordAuthor | Nanosized precipitates | - |
dc.subject.keywordAuthor | Austenitic stainless steel | - |
dc.subject.keywordAuthor | Void swelling | - |
dc.subject.keywordAuthor | Nano indentation | - |
dc.subject.keywordAuthor | Heavy ion irradiation | - |
dc.subject.keywordPlus | MICROSTRUCTURE EVOLUTION | - |
dc.subject.keywordPlus | BEHAVIOR | - |
dc.subject.keywordPlus | INDENTATION | - |
dc.subject.keywordPlus | TEMPERATURE | - |
dc.subject.keywordPlus | DISPERSION | - |
dc.subject.keywordPlus | HARDNESS | - |
dc.subject.keywordPlus | FISSION | - |
dc.subject.keywordPlus | NEUTRON | - |
dc.subject.keywordPlus | ALLOYS | - |
dc.subject.keywordPlus | DEFORMATION | - |
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