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Effects of Cr Carbides Formation on the High Temperature Creep Property of Alloy 690 for Steam Generator Tube Material
증기발생기 전열관용 Alloy 690 소재의 크리프 특성에 미치는 탄화물 형성의 영향
Hyung Kyu Kim, Seokmin Hong, Jongmin Kim, Min-Chul Kim, Young-Kook Lee
김형규, 홍석민, 김종민, 김민철, 이영국
Korean J. Met. Mater. 2023;61(4):301-309.   Published online 2023 Mar 22
DOI: https://doi.org/10.3365/KJMM.2023.61.4.301

Abstract
The creep properties of Alloy 690, used as a steam generator tube material in nuclear power plants, were evaluated at 650°C, 750°C, and 850°C. The parameters of creep life prediction models were derived using the Larson-Miller (LM), Manson-Haferd (MH), and Orr-Sherby-Dorn (OSD) models, to use as mechanical properties under a..... More

                
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

                
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