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Korean J. Met. Mater.
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Korean Journal of Metals and Materials
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SA508 Gr.4N Ni-Cr-Mo계 고강도 원자로압력용기용 저합금강의 템퍼취화 거동에 미치는 이상영역 열처리의 영향
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홍석민, 이초롱, 이봉상, 김홍덕, 김민철
Korean J. Met. Mater.
2023;61(10):729-740. Published online 2023 Sep 25
DOI:
https://doi.org/10.3365/KJMM.2023.61.10.729
Abstract
To analyze the effects of intercritical heat treatment on the temper embrittlement of SA508 Gr.4N steels, two model alloys with different phosphorus (P) contents were fabricated. Each sample was heat treated by applying a conventional heat treatment process (quenching-tempering) with/without an intercritical heat treatment process (IHT) and a step-cooling heat.....
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압력 용기 재료 SA508에서 열적 처리에 따른 입계 파괴의 원인
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김성수, 정종엽, 김영석
Korean J. Met. Mater.
2021;59(9):589-601. Published online 2021 Aug 4
DOI:
https://doi.org/10.3365/KJMM.2021.59.9.589
Abstract
Intergranular(IG) fracture due to thermal treatment has been reported in a reactor pressure vessel(RPV) steel of Russian light water reactor in last decade. This is attributed to grain boundary segregation of phosphorus (P) or precipitation of carbide, etc.. This is a finding a difference in microstructure before and after IG.....
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Web of Science 3
Crossref 3
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소형펀치 파단에너지 천이곡선을 활용한 원자로용기강의 천이온도 평가
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이태경, 홍석민, 김종민, 김민철, 장재일
Korean J. Met. Mater.
2020;58(8):522-532. Published online 2020 Jul 27
DOI:
https://doi.org/10.3365/KJMM.2020.58.8.522
Abstract
The small punch (SP) test is one of the small specimen test techniques, and standardization of the SP test method for evaluating the mechanical properties of metallic materials is in progress. In this study, the impact transition temperature of reactor pressure vessel steels (RPV) in nuclear power plants was estimated.....
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SA508 Gr.3 상용 원자로용기강의 두께방향 미세조직 변화가 인장 및 충격특성에 미치는 영향
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홍석민, 이초롱, 김민철, 이봉상
Korean J. Met. Mater.
2017;55(11):752-759. Published online 2017 Oct 31
DOI:
https://doi.org/10.3365/KJMM.2017.55.11.752
Abstract
In this study, the effects of microstructural variations in heavy-section reactor pressure vessel (RPV) steels on tensile and Charpy impact properties were investigated. Two PRV blocks, OPR1000 and APR1400 (ORV, ARV) were taken from the archive materials used in Korea standard nuclear power plants. Test specimens were sampled from five.....
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압력 용기 재료 SA508에서 열적 처리에 따른 입계 파괴의 원인
Published online 1999 Nov 30
Abstract
Intergranular(IG) fracture due to thermal treatment has been reported in a reactor pressure vessel(RPV) steel of Russian light water reactor in last decade. This is attributed to grain boundary segregation of phosphorus (P) or precipitation of carbide, etc.. This is a finding a difference in microstructure before and after IG cracking; this cannot...
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