DC Field | Value | Language |
---|---|---|
dc.contributor.author | Kim, Hyunmyung | ko |
dc.contributor.author | Jang, Hun | ko |
dc.contributor.author | Subramanian, Gokul Obulan | ko |
dc.contributor.author | Kim, Chaewon | ko |
dc.contributor.author | Jang, Changheui | ko |
dc.date.accessioned | 2018-08-20T07:47:15Z | - |
dc.date.available | 2018-08-20T07:47:15Z | - |
dc.date.created | 2018-08-01 | - |
dc.date.created | 2018-08-01 | - |
dc.date.created | 2018-08-01 | - |
dc.date.created | 2018-08-01 | - |
dc.date.issued | 2018-08 | - |
dc.identifier.citation | JOURNAL OF NUCLEAR MATERIALS, v.507, pp.1 - 14 | - |
dc.identifier.issn | 0022-3115 | - |
dc.identifier.uri | http://hdl.handle.net/10203/244818 | - |
dc.description.abstract | High 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.language | English | - |
dc.publisher | ELSEVIER SCIENCE BV | - |
dc.title | Development of alumina-forming duplex stainless steels as accident-tolerant fuel cladding materials for light water reactors | - |
dc.type | Article | - |
dc.identifier.wosid | 000438019800001 | - |
dc.identifier.scopusid | 2-s2.0-85046012966 | - |
dc.type.rims | ART | - |
dc.citation.volume | 507 | - |
dc.citation.beginningpage | 1 | - |
dc.citation.endingpage | 14 | - |
dc.citation.publicationname | JOURNAL OF NUCLEAR MATERIALS | - |
dc.identifier.doi | 10.1016/j.jnucmat.2018.04.027 | - |
dc.contributor.localauthor | Jang, Changheui | - |
dc.contributor.nonIdAuthor | Jang, Hun | - |
dc.contributor.nonIdAuthor | Kim, Chaewon | - |
dc.description.isOpenAccess | N | - |
dc.type.journalArticle | Article | - |
dc.subject.keywordAuthor | Accident-tolerant fuel cladding | - |
dc.subject.keywordAuthor | Alumina-forming duplex stainless steel | - |
dc.subject.keywordAuthor | High-temperature steam oxidation | - |
dc.subject.keywordAuthor | PWR autoclave corrosion | - |
dc.subject.keywordAuthor | Tensile strength | - |
dc.subject.keywordPlus | CORROSION BEHAVIOR | - |
dc.subject.keywordPlus | MECHANICAL-PROPERTIES | - |
dc.subject.keywordPlus | HEAT-TREATMENT | - |
dc.subject.keywordPlus | FECRAL ALLOYS | - |
dc.subject.keywordPlus | PRECIPITATION | - |
dc.subject.keywordPlus | EMBRITTLEMENT | - |
dc.subject.keywordPlus | TEMPERATURE | - |
dc.subject.keywordPlus | MICROSTRUCTURE | - |
dc.subject.keywordPlus | ENVIRONMENTS | - |
dc.subject.keywordPlus | DUCTILITY | - |
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