File Download

  • Find it @ UNIST can give you direct access to the published full text of this article. (UNISTARs only)
Related Researcher

손동성

Sohn, Dong-Seong
Read More

Views & Downloads

Detailed Information

Cited time in webofscience Cited time in scopus
Metadata Downloads

Full metadata record

DC Field Value Language
dc.citation.endPage 213 -
dc.citation.number 1 -
dc.citation.startPage 207 -
dc.citation.title NUCLEAR ENGINEERING AND TECHNOLOGY -
dc.citation.volume 51 -
dc.contributor.author Jung, Moo Young -
dc.contributor.author Baik, Youl -
dc.contributor.author Choi, Yong -
dc.contributor.author Sohn, Dong-Seong -
dc.date.accessioned 2023-12-21T19:38:25Z -
dc.date.available 2023-12-21T19:38:25Z -
dc.date.created 2019-01-25 -
dc.date.issued 2019-02 -
dc.description.abstract Corrosion and mechanical behavior of the hot-rolled 0.5%Gd-0.8%B-stainless steel to develop a spent nuclear fuel storage material was studied in a simulated nuclear waste treatment condition with rolling condition. The austenite and ferrite phases of the 0.5%Gd-0.8%B-stainless steels are about 88:12. The average austenite and ferrite grain size of the plane normal to rolling, transverse and normal directions of the hot rolled specimens are about 5.08, 8.94, 19.35, 23.29, 26.00 and 18.11 [m], respectively. The average micro-hardness of the as-cast specimen is 200.4 Hv, whereas, that of the hot-rolled specimen are 220.1, 204.7 and 203.5 [Hv] for the plane normal to RD, TD and ND, respectively. The UTS, YS and elongation of the as-cast and the hot-rolled specimen are 699, 484 [MPa], 34.0%, and 654, 432 [MPa] and 33.3%, respectively. The passivity was observed both for the as-cast and the hot rolled specimens in a simulated nuclear waste solution. The corrosion potential and corrosion rate of the as-casted specimens are −343 [mVSHE] and 3.2610−7 [A/cm2], whereas, those of the hot rolled specimens with normal to ND, RD and TD are −630, −512 and −620 [mVSHE] and 6.1210−7, 1.0410−6 and 6.9210−7 [A/cm2], respectively. Corrosion tends to occur preferentially Cr and B rich area. -
dc.identifier.bibliographicCitation NUCLEAR ENGINEERING AND TECHNOLOGY, v.51, no.1, pp.207 - 213 -
dc.identifier.doi 10.1016/j.net.2018.08.017 -
dc.identifier.issn 1738-5733 -
dc.identifier.scopusid 2-s2.0-85060934329 -
dc.identifier.uri https://scholarworks.unist.ac.kr/handle/201301/25799 -
dc.identifier.url https://www.sciencedirect.com/science/article/pii/S1738573318302535?via%3Dihub -
dc.identifier.wosid 000456341600021 -
dc.language 영어 -
dc.publisher KOREAN NUCLEAR SOC -
dc.title Corrosion and mechanical properties of hot-rolled 0.5%Gd-0.8%B-stainless steels in a simulated nuclear waste treatment solution -
dc.type Article -
dc.description.isOpenAccess TRUE -
dc.relation.journalWebOfScienceCategory Nuclear Science & Technology -
dc.identifier.kciid ART002433506 -
dc.relation.journalResearchArea Nuclear Science & Technology -
dc.description.journalRegisteredClass scie -
dc.description.journalRegisteredClass scopus -
dc.description.journalRegisteredClass kci -
dc.subject.keywordAuthor Gd-B-stainless steel -
dc.subject.keywordAuthor Corrosion -
dc.subject.keywordAuthor Neutron absorbing materials -
dc.subject.keywordPlus 316L STAINLESS-STEEL -

qrcode

Items in Repository are protected by copyright, with all rights reserved, unless otherwise indicated.