연구동향 분석
박사

원자로 용기 SA508 Grade 3 소재의 스테인리스강 클래딩시 입열량과 결정립 크기 변화에 따른 UCC 발생여부와 기준 마련에 관한 연구 = A Study on UCC Occurrence by the Change of Heat Input and Grain Size in SA508 Grade 3 Material used for Nuclear Reactor Vessel and Standard Preparation for UCC

조성우 2020년

논문상세정보
인용/피인용
' 원자로 용기 SA508 Grade 3 소재의 스테인리스강 클래딩시 입열량과 결정립 크기 변화에 따른 UCC 발생여부와 기준 마련에 관한 연구 = A Study on UCC Occurrence by the Change of Heat Input and Grain Size in SA508 Grade 3 Material used for Nuclear Reactor Vessel and Standard Preparation for UCC' 의 주제별 논문영향력
논문영향력 선정 방법
논문영향력 요약
주제
  • Cladding
  • Coarse grain practice
  • Delta ferrite
  • Ferrite Number
  • Fine grain practice
  • SA508 grade 3 class1
  • Stainless steel
  • Underclad cracking(UCC)
  • high heat input
  • nuclear reactor pressure vessel
  • overlay
  • strip submerged arc cladding
동일주제 총논문수 논문피인용 총횟수 주제별 논문영향력의 평균
146 0

0.0%

' 원자로 용기 SA508 Grade 3 소재의 스테인리스강 클래딩시 입열량과 결정립 크기 변화에 따른 UCC 발생여부와 기준 마련에 관한 연구 = A Study on UCC Occurrence by the Change of Heat Input and Grain Size in SA508 Grade 3 Material used for Nuclear Reactor Vessel and Standard Preparation for UCC' 의 참고문헌

  • [6] ASME Boiler and Pressure Vessel Code, American Society of Mechanic al Engineers, New York, NY.
  • [1] 10 CFR Part 50, “Domestic Licensing of Production and Utilization Facilities,” U.S. Nuclear Regulatory Commission, Washington, DC.
  • [13] Van der Boom, J. E., and Mulder, J. P. F., "Mechanical Properties of S trip Clad Weld Heat-Affected Zones Determined for Steels ASTEM A 508, cl. 2, A533, Gr. B, CI. 1, A302, Gr. B and A387, Gr. D in View of Susceptibility to Stress Relief Cracking," Welding Research Internation al, Vol. 2, No. 2, 1972.
  • Under-Clad CrackingPVRC Task Group Re port , Oak Ridge National Laboratory , Heavy Section Steel Technology Program
    Paper No . 5
  • Specification for Quenched and Tempered Vacuum Tre atedCarbon and Alloy Steel Forgings for Pressure Vessels
  • Reactor Vessels : WeldCladding-Base Metal Interaction , ” by T.R . Mager , E. Landerman , andC.J . Kubit , Westinghouse Nuclear Energy Systems Report
  • Mechanism of underclad cracking –combined effects of residual strain and heat-affected zone ductility
  • Internal Stresses in Thick Plates Weld-Overlaid with Austenitic Stainless Steel ( Report 2 )
    Vol . 5 , No . 1 , [1974]
  • Heat-Affected Zone Cracking in Low Alloy Stee ls During Stress Relief Heat Treatments , I.I.W
  • Cracking in Low-Alloy Steel Heat -Affected Zone under Austenitic Stainless Steel Weld Cladding , to be published in JOURNAL OP ENGINEERING MATERIALS AND TECH NOLOGY
  • Control of stainless steel weld cladd ing of low-alloy steel components
  • An Induction Heat Treatment ior Base Metal Regeneration after Weld Cladding , private i nformation
    [1974]
  • A Review of underclad craking in pre ssure-vessel components 197/August 1974 , WRC bulletin
  • A Review of Cracking Associated with Weld Deposited Cladding in Operating PWR Plants , by W. Bamford and R.D . Rishel , Westinghouse Electric Company Report