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Effects of Intercritical Heat Treatment on the Temper Embrittlement of SA508 Gr.4N Ni-Cr-Mo High Strength Low Alloy Steels for Reactor Pressure Vessels
SA508 Gr.4N Ni-Cr-Mo계 고강도 원자로압력용기용 저합금강의 템퍼취화 거동에 미치는 이상영역 열처리의 영향
Seokmin Hong, Cho-Long Lee, Bong-Sang Lee, Hong-Deok Kim, Min-Chul Kim
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..... More

                
Effects of Microstructure Variation on Tensile and Charpy Impact Properties in Heavy-Section SA508 Gr.3 Low Alloy Steels for Commercial Reactor Pressure Vessel
SA508 Gr.3 상용 원자로용기강의 두께방향 미세조직 변화가 인장 및 충격특성에 미치는 영향
Seokmin Hong, Cholong Lee, Min-Chul Kim, Bong-Sang Lee
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..... More

       Crossref 5
Effects of Cooling Rate by Double Austenitizing Tempering Treatment on the Microstructure and Mechanical Properties in Low Alloy Steel
저합금강의 이중 오스테나이징 템퍼링에서 냉각 속도에 따른 미세조직 및 기계적 특성 변화
Gyeong-Hoo Kim, Jae-Ho Jang, Sung-Hwan Kim, Byung-Jun Kim, Keun-Yong Sohn, Dae-Geun Nam
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..... More

       Crossref 1
Effects of Induction Heat Bending and Heat Treatment on the Boric Acid Corrosion of Low Alloy Steel Pipe for Nuclear Power Plants
Ki-Tae Kim, Min-Chul Shin, Hyun-Young Chang, Heung-Bae Park, Gi-Ho Sung, Young-Sik Kim
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... More
       Crossref 2
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