연구동향 분석

Grade 91 강의 고온 균열진전 실험 결과와 설계 물성치의 비교

이형연(Hyeong-Yeon Lee) 김우곤(Woo-Gon Kim) 김낙현(Nak-Hyun Kim) 2015년

논문상세정보
인용/피인용
' Grade 91 강의 고온 균열진전 실험 결과와 설계 물성치의 비교' 의 주제별 논문영향력
논문영향력 선정 방법
논문영향력 요약
주제
  • 기계공학
  • creep(크리프)
  • creepcrackgrowth(크리프균열진전)
  • fatiguecrackgrowth(피로균열진전)
  • grade91steel(grade91강)
  • sodium-cooled fast reactor(소듐냉각고속로)
  • welded joint(용접접합부)
동일주제 총논문수 논문피인용 총횟수 주제별 논문영향력의 평균
951 0

0.0%

' Grade 91 강의 고온 균열진전 실험 결과와 설계 물성치의 비교' 의 참고문헌

  • 소듐 시험루프 내 소듐대 공기 열교환기의 고온 설계
    이형연 대한기계학회논문집 A 37 (5) : 665 ~ 671 [2013]
  • Time-Dependent Crack Growth Behavior for a SMAW Weldment of Gr.91 Steel
    Kim, W. G. International Journal of Pressure Vessel and Piping 110 : 66 ~ 71 [2013]
  • RCC-MRx, Section III Tome 6, 2012, Probationary Phase Rules, 2012 Edition
    AFCEN
  • RCC-MRx, Section III Subsection Z, Appendix A3, 2012 Edition
    AFCEN [2012]
  • RCC-MRx, Section III Subsection Z, Appendix A16, 2012, Guide for Prevention of Fast Fracture, 2010Edition (Draft)
    AFCEN [2012]
  • RCC-MRx, Section III Subsection B, Class 1 N1RX, 2012, Reactor Components Its Auxiliary Systems and Supports, 2012 Edition
    AFCEN [2012]
  • R5, 2003, Assessment Procedure for the High Temperature Response of Structures, Issue 3
    British Energy Generation Ltd [2003]
  • Mechanical Behavior of HTR Materials : Developments in Support of Defect Assessment, Structural Integrity and Lifetime Evaluation
    Ancelet, O. Proceedings of ICAPP 2007 [2007]
  • High temperature design and damage evaluation of a helical type sodium-to-air heat exchanger in a sodium-cooled fast reactor
    이형연 Journal of Mechanical Science and Technology 27 (9) : 2729 ~ 2735 [2013]
  • Evaluation of Creep-Fatigue Damage for Hot Gas Duct Structure of the NHDD Plant
    Lee, H. Y. Journal of Pressure Vessel Technology, Transactions of ASME 132 (2) : 1 ~ 8 [2010]
  • Evaluation of Creep Strength Reduction Factors for Welded Joints of Modified 9Cr-1Mo Steel
    Tabuchi, M. J. Pressure Vessel Technol 134 (3) : 031401 ~ [2012]
  • EU FP7 MATTER (MATerial Testing and Rules)Project Domain 2 (Pre-Normative R&D for Codes and Standards) Technical Meeting
    [2012]
  • Design Concept of Advanced Sodium-Cooled Fast Reactor and Related R&D in Korea
    Kim, Y. I. Science and Technology of Nuclear Installations 2013 [2013]
  • Creep-Fatigue Damage for a Structure with Dissimilar Metal Welds of Mod 9Cr-1Mo and 316L Stainless Steel
    Lee, H. Y. International Journal of Fatigue : 29 ~ [2007]
  • Assessment of the high-temperature crack behavior for a 316L stainless steel structure with defects
    Hyeong-Yeon Lee Journal of Mechanical Science and Technology 24 (2) : 481 ~ 487 [2010]
  • ASME Boiler and Pressure Vessel Code, Section III, 2013, Rules for Construction of Nuclear Power Plant Components, Div. 1, Subsection NH, Class 1Components in Elevated Temperature Service
    ASME [2013]
  • ASME Boiler and Pressure Vessel Code, Section II, 2013, Part D Proerties
    ASME [2013]
  • API 579-1/ASME FFS-1
    Fitness-For-Service [2007]