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안상준

Ahn, Sangjoon
UNIST RAdioactive NUclear Materials Lab.
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dc.citation.startPage 153137 -
dc.citation.title JOURNAL OF NUCLEAR MATERIALS -
dc.citation.volume 555 -
dc.contributor.author Lee, Myeongkyu -
dc.contributor.author Kim, Geon -
dc.contributor.author Jung, Yunsong -
dc.contributor.author Ahn, Sangjoon -
dc.date.accessioned 2023-12-21T15:08:30Z -
dc.date.available 2023-12-21T15:08:30Z -
dc.date.created 2021-09-07 -
dc.date.issued 2021-11 -
dc.description.abstract The radiation responses of two newly developed ferritic/martensitic steels, FC92-B and -N, were tested in comparison to reference alloys HT9 and Gr.92. Ion irradiations on the steels were performed up to 480 dpa at 475 degrees C using 3.5-MeV Fe++ ions with a helium pre-implantation of 1 appm/dpa. Void swelling and M2X precipitation were characterized using FE-TEM and EDS. Swelling resistance was the greatest in FC92-N, which showed suppressed void nucleation and growth. The swelling rate in FC92-N was determined as 0.005 %/dpa, indicating that FC92-N did not reach the steady-state swelling regime with void nucleation behavior. The least swelling-resistant alloy was HT9 with a swelling rate of 0.048 %/dpa. Cr-rich carbide, M2X, was observed in only 9Cr-FC92 series; however, its formation did not depend on radiation damage. This exceptional M2X evolution in FC92 series may be attributed to B and N alloying, which resulted in suppressed M23C6 carbide formation during metallurgical production and sequentially high C contents in the alloy solution of FC92 series. A narrower range (800 nm) of M2X evolution compared to that of cavity formation (1,000 nm) indicates that radiation-induced precipitation (RIP) is more sensitive to the injected interstitial effect. Precipitation-induced Cr depletion and preferential interstitial outward sinking to the free surface synergistically modified local chemical composition before void evolution and led to double-peak swelling by locally forming a low-alloyed zone. This study provides the first experimental evidence that RIP modifies the swelling-depth profiles and in turn, determines double-peak swelling in ion-irradiated steels. (C) 2021 Published by Elsevier B.V. -
dc.identifier.bibliographicCitation JOURNAL OF NUCLEAR MATERIALS, v.555, pp.153137 -
dc.identifier.doi 10.1016/j.jnucmat.2021.153137 -
dc.identifier.issn 0022-3115 -
dc.identifier.scopusid 2-s2.0-85109128417 -
dc.identifier.uri https://scholarworks.unist.ac.kr/handle/201301/53849 -
dc.identifier.url https://www.sciencedirect.com/science/article/pii/S0022311521003603?via%3Dihub -
dc.identifier.wosid 000686062700006 -
dc.language 영어 -
dc.publisher ELSEVIER -
dc.title Radiation-induced swelling and precipitation in Fe++ ion-irradiated ferritic/martensitic steels -
dc.type Article -
dc.description.isOpenAccess FALSE -
dc.relation.journalWebOfScienceCategory Materials Science, Multidisciplinary; Nuclear Science & Technology -
dc.relation.journalResearchArea Materials Science; Nuclear Science & Technology -
dc.type.docType Article -
dc.description.journalRegisteredClass scie -
dc.description.journalRegisteredClass scopus -
dc.subject.keywordAuthor Ferritic/martensitic steels -
dc.subject.keywordAuthor ion irradiation -
dc.subject.keywordAuthor swelling resistance -
dc.subject.keywordAuthor M2X precipitation -
dc.subject.keywordAuthor fast reactor cladding material -
dc.subject.keywordPlus FERRITIC-MARTENSITIC STEELS -
dc.subject.keywordPlus NEUTRON-IRRADIATION -
dc.subject.keywordPlus CR ALLOYS -
dc.subject.keywordPlus INJECTED INTERSTITIALS -
dc.subject.keywordPlus PURE IRON -
dc.subject.keywordPlus MICROSTRUCTURE -
dc.subject.keywordPlus DAMAGE -
dc.subject.keywordPlus EVOLUTION -
dc.subject.keywordPlus SILICON -
dc.subject.keywordPlus DPA -

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