The effect of Li 2 TiO 3 pebbles on the mechanical properties of ARAA under breeding blanket conditions
DC Field | Value | Language |
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dc.contributor.author | Jung, Yunsong | - |
dc.contributor.author | Park, Youngah | - |
dc.contributor.author | Ku, Duck Young | - |
dc.contributor.author | Park, Yi-Hyun | - |
dc.contributor.author | Gwon, Hyoseong | - |
dc.date.accessioned | 2024-07-21T02:30:23Z | - |
dc.date.available | 2024-07-21T02:30:23Z | - |
dc.date.issued | 2024-06 | - |
dc.identifier.issn | 2352-1791 | - |
dc.identifier.issn | 2352-1791 | - |
dc.identifier.uri | https://scholarworks.bwise.kr/gachon/handle/2020.sw.gachon/92027 | - |
dc.description.abstract | The breeding blanket serves as a critical element for achieving a self-sustaining tritium cycle and generating sufficient energy in fusion reactors. This study focuses on candidate materials of the helium-cooled solid breeder blanket designed for a demonstration fusion reactor breeding blanket in Korea. We conducted compatibility tests between advanced reduced-activation alloy (ARAA) and Li 2 TiO 3 pebbles at 550 degrees C for 28 days in He -0.1 vol% H 2 purge gas conditions. Surface oxidation on ARAA was observed regardless of pebble presence. Double oxide films comprised of Fe-rich and Cr-rich layers formed on the surface of ARAA with pebbles. Lithium deposition was verified in both contact and non -contact areas of ARAA. Despite surface oxidation, the impact on tensile strength and elongation was found to be negligible. | - |
dc.language | 영어 | - |
dc.language.iso | ENG | - |
dc.publisher | ELSEVIER | - |
dc.title | The effect of Li 2 TiO 3 pebbles on the mechanical properties of ARAA under breeding blanket conditions | - |
dc.type | Article | - |
dc.identifier.wosid | 001234151900001 | - |
dc.identifier.doi | 10.1016/j.nme.2024.101658 | - |
dc.identifier.bibliographicCitation | NUCLEAR MATERIALS AND ENERGY, v.39 | - |
dc.description.isOpenAccess | Y | - |
dc.identifier.scopusid | 2-s2.0-85190715926 | - |
dc.citation.title | NUCLEAR MATERIALS AND ENERGY | - |
dc.citation.volume | 39 | - |
dc.type.docType | Article | - |
dc.publisher.location | 네델란드 | - |
dc.subject.keywordAuthor | Breeding blanket | - |
dc.subject.keywordAuthor | Compatibility | - |
dc.subject.keywordAuthor | RAFM | - |
dc.subject.keywordAuthor | ARAA | - |
dc.subject.keywordAuthor | Li2TiO3 | - |
dc.subject.keywordPlus | FERRITIC-MARTENSITIC STEEL | - |
dc.subject.keywordPlus | CHEMICAL COMPATIBILITY | - |
dc.subject.keywordPlus | CORROSION SUSCEPTIBILITY | - |
dc.subject.keywordPlus | EUROFER97 | - |
dc.subject.keywordPlus | TITANATE | - |
dc.subject.keywordPlus | LI2TIO3 | - |
dc.subject.keywordPlus | ALLOY | - |
dc.relation.journalResearchArea | Nuclear Science & Technology | - |
dc.relation.journalWebOfScienceCategory | Nuclear Science & Technology | - |
dc.description.journalRegisteredClass | scie | - |
dc.description.journalRegisteredClass | scopus | - |
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