본문 바로가기 대메뉴 바로가기
Bong-Sang Lee(Professor)

INFO

  • AffiliationKorea Atomic Energy Research Institute
  • Majors Quantum Energy Chemical Engineering
  • Contact Information042-868-8561
  • Major재료공학
  • DegreePh.D.
  • Highest Level of Education한국과학기술원
  • E-Mail

Field of Research

Irradiation embrittlement and fracture mechanical integrity of reactor pressure boundary materials

Research Results

-  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

Book(in last five years)

-  원전기기건전성[2013-01-01] -  원전기기 건전성[2013-08-30]

Treatise

-  Characterization of phase fractions and misorientations on tempered bainitic/martensitic Ni-Cr-Mo low alloy RPV steel with various Ni contents[Metals & Materials Int. ,2013-01-01] -  Effect of Nickel Content on the Neutron Irradiation Embrittlement of N-Mo-Cr Steels[Metals & Materials Int. ,2013-01-01] -  Effects of boundary characteristics on resistance to temper embrittlement and segregation behavior of Ni-Co-Mo low alloy steel[Materials Sci. & Eng. A,2013-01-01] -  Evaluation of Microstructure and Mechanical Properties in a Thick Plate of G91 Steel and its Weld for High Temperature Nuclear System[Current Nanoscience,2014-02-01] -  Evaluation of microstructural parameters controlling cleavage fracture toughness in Mn-Mo-Ni low alloy steel[Materials Sci. & Eng. A,2013-01-01] -  Characterization of phase fractions and misorientations on tempered bainitic/martensitic Ni-Cr-Mo low alloy RPV steel with various Ni contents[ METALS AND MATERIALS INTERNATIONAL,2013-01-15] -  Evaluation of microstructural parameters controlling cleavage fracture toughness in Mn-Mo-Ni low alloy steel[ MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING,2013-01-15] -  Effects of boundary characteristics on resistance to temper embrittlement and segregation behavior of Ni-Co-Mo low alloy steel[ MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING,2013-01-15] -  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] -  Effect of Nickel Content on the Neutron Irradiation Embrittlement of N-Mo-Cr Steels[ METALS AND MATERIALS INTERNATIONAL,2013-11-01] -  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 boundary characteristics on resistance to temper embrittlement and segregation behavior of Ni-Cr-Mo low alloy steel[ MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING,2013-03-15] -  Evaluation of microstructural parameters controlling cleavage fracture toughness in Mn-Mo-Ni low alloy steel[ MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING,2013-05-15] -  Characterization of phase fraction and misorientations on tempered bainitic/martensitic Ni-Cr-Mo low alloy RPV steel with various Ni contents[ METALS AND MATERIALS INTERNATIONAL,2013-03-01] -  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]

Patent

-  템퍼취화 저항성이 향상된 니켈-크롬-몰리브덴계 저합금강 및 이의 제조방법[2014-01-01] -  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] -  RCC-ELB : RCC-MRx(알씨시-엠알엑스) 기반의 엘보우균열 파괴역학 해석 프로그램[2014-01-01] -  RCC-PTW : RCC-MRx(알씨시-엠알엑스) 기반의 배관 부분관통균열 파괴역학 해석 프로그램[2014-01-01] -  Bimo-MC : 바이모달 마스터커브 파괴특성 분석 프로그램[2014-01-01] -  RCC-TW : RCC-MRx 기반의 배관관통균열 파괴역학 해석 프로그램[2014-01-01]