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이봉상 교수

Bong-Sang Lee

INFO

  • 소속캠퍼스한국원자력연구원
  • 전공 양자에너지화학공학
  • 연락처042-868-8561
  • 출신전공재료공학
  • 학위박사
  • 최종출신대학한국과학기술원
  • 이메일

연구분야

원자로압력경계 재료의 조사취화 및 파괴역학 건전성

Irradiation embrittlement and fracture mechanical integrity of reactor pressure boundary materials

대표연구실적

-  B.S.Lee, M.C.Kim, J.H.Yoon, J.H.Hong, “Characterization of High Strength and High Toughness Ni-Mo-Cr Low Alloy Steels for Nuclear Application”, International Journal of Pressure Vessels and Piping 87 (2010) 74-80 -  B.S.Lee, M.C.Kim, M.W.Kim, J.H.Yoon, J.H.Hong, "Master Curve Techniques to Evaluate an Irradiation Embrittlement of Nuclear Reactor Pressure Vessels For a Long-Term Operation", International Journal of Pressure Vessels and Piping 85 (2008) 593-599 -  K.H. Lee, S.G. Park, M.C. Kim, and B.S. Lee, “Evaluation of Microstructural Parameters Controlling Cleavage Fracture Toughness in Mn-Mo-Ni Low Alloy Steels” , Materials Science and Engineering A 565 (2013) 15

논문(최근 5년)

-  Effects of Oxide on Fatigue Crack Growth Behavior of Type 347 Stainless Steel in PWR Water Conditions[Fatigue and Fracture of Engineering Materials and Structures,2015-07-01] -  Effects of Microstructural Variation on Charpy Impact Properties in Heavy-Section Mn-Mo-Ni Low Alloy Steels for Reactor Pressure Vessel[ METALS AND MATERIALS INTERNATIONAL,2016-02-01] -  Effects of tempering and PWHT on microstructures and mechanical properties of SA508 Gr.4N steel[ NUCLEAR ENGINEERING AND TECHNOLOGY,2014-06-01] -  Comparison of Fracture Properties in SA508 Gr.3 and Gr.4N High Strength Low Alloy Steels for Advanced Pressure Vessel Materials[ INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING,2015-07-01] -  SA508 Gr.3 Mn-Mo-Ni계 저합금강의 두께방향 깊이에 따른 탄화물의 석출거동과 천이영역 파괴인성의 변화[ KOREAN JOURNAL OF METALS AND MATERIALS,2015-12-01] -  소듐냉각고속로 압력용기용 Type 316H 스테인리스강의 고온 비탄성 반복변형 거동[ KOREAN JOURNAL OF METALS AND MATERIALS,2015-10-01] -  Fatigue crack growth behavior of austenitic stainless steel in PWR water coditions[Journal of Korean Institute of Metals and Materials,2015-04-01] -  Statistical analysis on the fluence factor of surveillance test data of Korean nuclear power plants[ NUCLEAR ENGINEERING AND TECHNOLOGY,2017-06-01] -  Comparison of Applicability of Current Transition TemperatureShift Models to SA533B-1 Reactor Pressure Vessel Steel of Korean Nuclear Reactors[ NUCLEAR ENGINEERING AND TECHNOLOGY,2017-08-01] -  Atom Probe Tomography Analysis of Nanostructure Evolution in Ni-Cr-Mo Low Alloy Steel under Neutron Irradiation[ JOURNAL OF MECHANICAL SCIENCE AND TECHNOLOGY,2017-08-01] -  Fatigue crack growth characteristics of nitrogen-alloyed type 347[ NUCLEAR ENGINEERING AND TECHNOLOGY,2017-04-01] -  Effects of microstructure variation on tensile and Charpy impact properties in heavy-sectione SA508 Gr.3 low alloy steels for commercial reactor pressure vessel[ KOREAN JOURNAL OF METALS AND MATERIALS,2017-11-01] -  Irradiation embrittlement behavior of Sa508 Gr.4N RPV steel model ALLOY[American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP,2016-07-17]

특허(최근 5년)

-  EMA-LUST (원자로용기 저인성 파손 안전도 평가 프로그램)[2016-01-01] -  PROFAS-RV 2 (원자로 압력용기 확률론적 파괴역학 안전도 평가 시스템 2)[2016-01-01] -  PROFAS-RV ver. 1.0 (원자로 압력용기 확률론적 파괴역학 안전도 평가 시스템 버전 1.0)[2015-01-01]

연구과제 수행 실적

원전재료 잠재열화 대응 원천기술 개발