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논문 기본 정보

자료유형
학술저널
저자정보
Eun Hee Jeong (Hanyang University) Jun Hwan Kim (Korea Atomic Energy Research Institute) Sung Ho Kim (Korea Atomic Energy Research Institute) Young Do Kim (Hanyang University)
저널정보
대한금속·재료학회 Metals and Materials International Metals and Materials International Vol.28 No.6
발행연도
2022.6
수록면
1,445 - 1,454 (10page)
DOI
10.1007/s12540-021-01031-5

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초록· 키워드

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To develop South Korea’s own SFR nuclear fuel cladding tube that has excellent high temperature creep characteristics,candidate alloys for a new cladding material that has better performance than the conventional Gr.92 (9Cr–2W–Nb–V) steelwere selected by conducting a high temperature tensile test and creep test for the candidate alloys fabricated by adequatelycombining precipitation and strengthening of alloy elements (C, Ta, Nb, V, N) with solid solution treatment and hardeningof alloy elements (Cr, Mo, W, B). Among the candidate alloys, two types—FC92B and FC92N—that had excellent creepcharacteristics were used to fabricate the cladding tubes. In the results of the creep test, when a cladding tube was fabricatedby using FC92N, which showed excellent creep performance in the air atmosphere, the creep performance declined. Afterthe creep tests of FC92B and FC92N cladding tubes, this study examined the microstructures of specimens and analyzedthe relationship between microstructure and creep rupture life. When the creep test was performed in the air and argon gasatmosphere, FC92N showed a larger increase in the thickness of an oxide layer than FC92B. It was determined that the FC92Balloy, in which 130 ppm of B was added, showed excellent creep performance in both the air and argon gas atmospheresbecause its oxidation resistance was relatively excellent compared to that of FC92N.

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