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Korean J. Met. Mater.
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SA508 Gr.1A 저합금강의 기계적특성에 미치는 이상영역열처리 및 Pre-tempering 열처리의 영향
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현세미, 홍석민, 김민철, 김종민, 손석수
Korean J. Met. Mater.
2024;62(8):593-601. Published online 2024 Jul 31
DOI:
https://doi.org/10.3365/KJMM.2024.62.8.593
Abstract
To apply the leak-before-break (LBB) concept to the main steam line piping of nuclear power plants, the use of SA508 Gr.1A low-alloy steel is being considered. To increase the LBB safety margin, it is essential to improve the strength and toughness of the material. In this study, intercritical heat treatment.....
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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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Korean J. Met. Mater.
2019;57(9):575-581. Published online 2019 Aug 21
DOI:
https://doi.org/10.3365/KJMM.2019.57.9.575
Abstract
Alloys of Fe-12Cr-0.3C-4Mn-(13, 14, 15)Cu (wt%) were cast using an induction furnace. They were structurally heterogeneous composites that consisted of a relatively stiff α-Fe matrix and a soft (Cu, Mn)-rich secondary phase. They were developed as self-lubricating, wear-resistant metals. Since the formation of oxides plays an important role in wear,.....
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Web of Science 4
Crossref 6
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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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Crossref 5
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저합금강의 이중 오스테나이징 템퍼링에서 냉각 속도에 따른 미세조직 및 기계적 특성 변화
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김경후, 장재호, 김성환, 김병준, 손근용, 남대근
Korean J. Met. Mater.
2017;55(8):559-565. Published online 2017 Aug 1
DOI:
https://doi.org/10.3365/KJMM.2017.55.8.559
Abstract
Spent nuclear fuel is stored and transported in cask bodies, but they become embrittled with the passage of time resulting in lattice defects due to neutron irradiation. Cask bodies made by the quenching and tempering (QT) treatment are not safe and are hard to store because of embrittlement caused by.....
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Korean J. Met. Mater.
2016;54(11):817-825. Published online 2016 Nov 5
DOI:
https://doi.org/10.3365/KJMM.2016.54.11.817
Abstract
In many plants, including nuclear power plants, pipelines are composed of numerous fittings such as elbows. When plants use these fittings, welding points need to be increased, and the number of inspections also then increases. As an alternative to welding, the pipe bending process forms bent pipe by applying strain...
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