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An Examination of Bronze Vessel Technology in the Unified Silla Period: Case Study on the Bronzes Excavated from Gwanbuk-ri Site in Buyeo
통일신라 청동용기류의 제작기술 고찰: 부여 관북리 백제유적 출토 유물을 중심으로
So Jin Kim, Woo Rin Han, Young Do Kim
김소진, 한우림, 김영도
Korean J. Met. Mater. 2024;62(5):393-401.   Published online 2024 May 5
DOI: https://doi.org/10.3365/KJMM.2024.62.5.393

Abstract
Archaeological excavations in Buyeo had revealed Bronze vessels interred within a hole in the building at the Gwanbuk-ri site. These bronze vessels are dated to the Unified silla period (9-10th centuries). To identify the bronze vessels’ manufacturing technology, metallurgical analyses were carried out using Optical Microscopy, SEM-EDS and EPMA. The..... More

                
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

                
The Cause of Intergranular (IG) Fracture by Thermal Embrittlement in SA508 of Reactor Pressure Vessel (RPV) Steel
압력 용기 재료 SA508에서 열적 처리에 따른 입계 파괴의 원인
Sung Soo Kim, Jung Jong Yeob, Young Suk Kim
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..... More

                   Web of Science 3  Crossref 3
Evaluation of Transition Temperature in Reactor Pressure Vessel Steels 6using the Fracture Energy Transition Curve from a Small Punch Test
소형펀치 파단에너지 천이곡선을 활용한 원자로용기강의 천이온도 평가
Tae-kyung Lee, Seokmin Hong, Jongmin Kim, Min-Chul Kim, Jae-il Jang
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..... More

                
Effects of Molybdenum on HIC Susceptibility in Normalized Pressure Vessel Steels for Sour Service Applications
Kijung Park, Dae Hyun Cho, Min-Ho Park, Cheol-Woong Yang
Korean J. Met. Mater. 2019;57(7):405-411.   Published online 2019 Jun 5
DOI: https://doi.org/10.3365/KJMM.2019.57.7.405

Abstract
This paper discusses a molybdenum-added alloy design for normalized pressure vessel steels, to reduce hydrogen induced cracking (HIC) and inhibit crack propagation. The change in microstructure produced by the modified alloy composition was analyzed to determine its effect on HIC characteristics. The microstructural change was observed by optical microscopy, hardness..... More

                   Web of Science 6  Crossref 5
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
The Cause of Intergranular (IG) Fracture by Thermal Embrittlement in SA508 of Reactor Pressure Vessel (RPV) Steel
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... More
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