연구동향 분석

Alloy 600TT 증기발생기 전열관내 일렬 원주방향 표면 일차수응력 부식균열 성장에 미치는 균열 간격의 영향 고찰

허은주(Eun-Ju Heo) 김종성(Jong Sung Kim) 전준영(Jun-Young Jeon) 김윤재(Yun-Jae Kim) 2015년

논문상세정보
인용/피인용
' Alloy 600TT 증기발생기 전열관내 일렬 원주방향 표면 일차수응력 부식균열 성장에 미치는 균열 간격의 영향 고찰' 의 주제별 논문영향력
논문영향력 선정 방법
논문영향력 요약
주제
  • 기계공학
  • alloy 600tt(니켈기합금 600tt)
  • collinearcircumferentialsurfacepwscc(일렬원주방향표면일차수응력부식균열)
  • damagemechanics(손상역학)
  • finite element analysis (유한요소해석)
  • growthbehavior(성장거동)
  • pwscc initiation model(일차수응력부식균열 발생 모델)
  • steam generator tubes(증기발생기 전열관)
동일주제 총논문수 논문피인용 총횟수 주제별 논문영향력의 평균
1,162 0

0.0%

' Alloy 600TT 증기발생기 전열관내 일렬 원주방향 표면 일차수응력 부식균열 성장에 미치는 균열 간격의 영향 고찰' 의 참고문헌

  • Stress-Intensity Factor Equations for Cracks in Three-Dimensional Finite Bodies Subjected to Tension and Bending Loads
    Newman, J. [1984]
  • Stress Corrosion Cracking Initiation Model for Stainless Steel and Nickel Alloys
    EPRI [2009]
  • Steam Generator Reference Book, Revision 1
    EPRI [1994]
  • Simulia, User’s Manuals for ABAQUS, Ver.6.13
  • PWSCC Prediction Guidelines
    EPRI [1994]
  • Final Report-Generic Aging Lessons Learned (GALL) Report
    USNRC [2010]
  • Evaluation of Crack Growth Rate for Alloy 600TT SG Tubing in Primary and Faulted Secondary Water Environments
    Nakata, K. Okabe, T. Ozawa, M. Sato, M. Tsuruta, T. Yamamoto, Y. Proceedings of the 12th Int. Conf. on Environmental Degradation of Materials in Nuclear Power System-Water Reactors-TMS : 1243 ~ 1252 [2005]
  • Development of Technologies for Improving Integrity of Nuclear Steam Generators
    KAERI [2004]
  • Degradation of Alloy 600 Steam Generator Tubes in Operating Pressurized Water Reactor Power Plants
    Hwang, S.S. Corrosion Engineering 59 (9) : 821 ~ 827 [2003]
  • An Investigation on Multiple Axial Surface PWSCC Growth Behaviors in Primary Alloy 600 Components Using the PWSCC Initiation Model and Damage Mechanics Approach
    Kim, J.S. Proceedings of the ASME PVP 2014 [2014]
  • An Analysis of Primary Water Stress Corrosion Cracking in PWRSteam Generators
    Scott, P.M. Proceedings of the Specialists Meeting on Operating Experience with Steam Generators : 5 ~ 6 [1991]
  • ASME B&PV Code
  • A Model of Caustic Stress Corrosion Crack Initiation and Growth in Alloy 600
    EPRI [1994]
  • A Finite Element Ductile Failure Simulation Method Using Stress-Modified Fracture Strain Model
    Kim, N.H. Engineering Fracture Mechanics 78 (1) : 124 ~ 137 [2011]