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    소형펀치 파단에너지 천이곡선을 활용한 원자로용기강의 천이온도 평가 = Evaluation of Transition Temperature in Reactor Pressure Vessel Steels using the Fracture Energy Transition Curve from a Small Punch Test

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    https://www.riss.kr/link?id=A106972281

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    다국어 초록 (Multilingual Abstract) kakao i 다국어 번역

    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 using the draft standard SP test method. The SP fracture energy (ESP) and normalized SP fracture energy (ENSP) of the RPV steels were evaluated at various temperatures, and their transition curves were derived and compared to the transition curve in the Charpy V notch (CVN) test. The SP transition region appeared at a much lower temperature range than that of the CVN owing to the size and notch effect. Ductile brittle transition temperature (DBTT) in the SP transition curve showed a linear relationship with DBTT and T41J in the CVN transition curve. The ductile to brittle transition behaviors of SP specimens were analyzed using fractographs and compared with the transition curves in ESP and ENSP. ENSP started to decrease at the temperature at which the SP ductile to brittle transition behavior occurred, and this means that the ENSP transition curves were in good agreement with transition behavior in the SP test. However, the ESP transition curves did not match transition behavior. Using DBTT in the ENSP transition curve is appropriate to estimate the CVNDBTT and T41J.
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    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 reacto...

    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 using the draft standard SP test method. The SP fracture energy (ESP) and normalized SP fracture energy (ENSP) of the RPV steels were evaluated at various temperatures, and their transition curves were derived and compared to the transition curve in the Charpy V notch (CVN) test. The SP transition region appeared at a much lower temperature range than that of the CVN owing to the size and notch effect. Ductile brittle transition temperature (DBTT) in the SP transition curve showed a linear relationship with DBTT and T41J in the CVN transition curve. The ductile to brittle transition behaviors of SP specimens were analyzed using fractographs and compared with the transition curves in ESP and ENSP. ENSP started to decrease at the temperature at which the SP ductile to brittle transition behavior occurred, and this means that the ENSP transition curves were in good agreement with transition behavior in the SP test. However, the ESP transition curves did not match transition behavior. Using DBTT in the ENSP transition curve is appropriate to estimate the CVNDBTT and T41J.

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    참고문헌 (Reference)

    1 E. Altstadt, 654 : 309-, 2016

    2 M. Bruchhausen, 155 : 27-, 2017

    3 B. Gülçimen, 105 : 28-, 2013

    4 K. Turba, 111 : 115-, 2013

    5 M. A. Contreras, 31 : 727-, 2008

    6 J. -M. Baik, 17 : 1443-, 1983

    7 M. Brumovsky, 2018

    8 M. Lorenzo, 614 : 319-, 2014

    9 J. S. Ha, 75 : 707-, 1998

    10 T. E. García, 582 : 708-, 2014

    1 E. Altstadt, 654 : 309-, 2016

    2 M. Bruchhausen, 155 : 27-, 2017

    3 B. Gülçimen, 105 : 28-, 2013

    4 K. Turba, 111 : 115-, 2013

    5 M. A. Contreras, 31 : 727-, 2008

    6 J. -M. Baik, 17 : 1443-, 1983

    7 M. Brumovsky, 2018

    8 M. Lorenzo, 614 : 319-, 2014

    9 J. S. Ha, 75 : 707-, 1998

    10 T. E. García, 582 : 708-, 2014

    11 Y. Nishiyama, 56 : 4510-, 2008

    12 J. Blach, 16 : 1397-, 2009

    13 J. R. Foulds, EPRI

    14 M. C. Kim, 235 : 1799-, 2005

    15 E. Altstadt, 100 : 191-, 2019

    16 M. Bruchhausen, 86 : 2-, 2016

    17 J. Adams, 2015

    18 G. E. Lucas, 21A : 1105-, 1990

    19 B. C. Choi, 39 : 165-, 2001

    20 김진원, "소형펀치시험을 통한 열화 주조 스테인리스강의 인장물성치 평가에 대한 신뢰성 분석" 대한금속·재료학회 52 (52): 407-419, 2014

    21 이민수, "금속 재료의 국부 변형 거동 분석 방법과 연구 동향: 리뷰" 대한금속·재료학회 56 (56): 635-644, 2018

    22 Junfeng Nie, "Study on the irradiation effect of mechanical properties of RPV steels using crystal plasticity model" 한국원자력학회 51 (51): 501-509, 2019

    23 M. A. Sokolov, "Small Specimen Test Techniques: 4th volume" ASTM International 365-369, 2002

    24 W. R. Corwin, "Small Specimen Test Techniques Applied to Nuclear Reactor Vessel Thermal Annealing and Plant Life Extension" ASTM international 217-, 1993

    25 S. Arunkumar, "Overview of Small Punch Test" 대한금속·재료학회 26 (26): 719-738, 2020

    26 Javier Vivas, "Microstructural Degradation and Creep Fracture Behavior of Conventionally and Thermomechanically Treated 9% Chromium Heat Resistant Steel" 대한금속·재료학회 25 (25): 343-352, 2019

    27 이기형, "Effects of Tempering and PWHT on Microstructures and Mechanical Properties of SA508 GR.4N Steel" 한국원자력학회 46 (46): 413-422, 2014

    28 윤지현, "Comparison of applicability of current transition temperature shift models to SA533B-1 reactor pressure vessel steel of korean nuclear reactors" 한국원자력학회 49 (49): 1109-1112, 2017

    29 "CWA 15627" 2007

    30 "ASTM Work Item number WK61832, Annual Book of ASTM Standards"

    31 "ASTM Work Item number WK47431, Annual Book of ASTM Standards"

    32 "ASTM E23-18, Annual Book of ASTM Standards"

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    학술지 이력

    학술지 이력
    연월일 이력구분 이력상세 등재구분
    2023 평가 해외DB학술지평가 신청대상 (해외등재 학술지 평가)
    2020-01-01 등재 등재학술지 유지 (해외등재 학술지 평가) KCI등재
    2010-01-01 등재 등재학술지 유지 (등재유지) KCI등재
    2009-12-29 학회명변경 한글명 : 대한금속ㆍ재료학회 -> 대한금속·재료학회 KCI등재
    2008-01-01 등재 등재학술지 유지 (등재유지) KCI등재
    2006-01-01 등재 등재학술지 유지 (등재유지) KCI등재
    2004-01-01 등재 등재학술지 유지 (등재유지) KCI등재
    2001-01-01 등재 등재학술지 선정 (등재후보2차) KCI등재
    1998-07-01 등재 등재후보학술지 선정 (신규평가) KCI등재후보
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    기준연도 WOS-KCI 통합IF(2년) KCIF(2년) KCIF(3년)
    2016 1.24 1.12 0.9
    KCIF(4년) KCIF(5년) 중심성지수(3년) 즉시성지수
    0.73 0.6 0.835 0.2
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