연구동향 분석

미국의 건식저장 캐니스터에서의 CISCC 연구에 대한 검토

박형규 박광헌 2018년

논문상세정보
    • 저자 박형규 박광헌
    • 제어번호 105976046
    • 학술지명 방사성폐기물학회지
    • 권호사항 Vol. 16 No. 4 [ 2018 ]
    • 발행처 한국방사성폐기물학회
    • 자료유형 학술저널
    • 수록면 455-472
    • 언어 Korean
    • 출판년도 2018
    • 등재정보 KCI등재
    • 소장기관 경북대학교 중앙도서관 서울대학교 중앙도서관 연세대학교 원주학술정보원 연세대학교 원주학술정보원
    • 판매처
    유사주제 논문( 0)
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' 미국의 건식저장 캐니스터에서의 CISCC 연구에 대한 검토' 의 참고문헌

  • 사용후핵연료 건식저장을 위한 기체강제순환 건조장치 예비설계
  • 사용후핵연료 건식저장용기의 콘크리트 받침대에 대한 구조해석평가
    김동학 [2006]
  • 경수로 사용후핵연료 건식저장을 위한 진공건조공정 개발
    백창열 [2016]
  • 경수로 사용후핵연료 건식저장시스템의 격납감시 기술현황 분석
    백창열 [2016]
  • 건식저장용기에 대한 전복해석의 검증시험
    김동학 [2006]
  • Weld Residual Stress Final Results and CISCC Model Development
    C. Bryan [2016]
  • U.S. DOE Spent Nuclear Fuel Storage &Transportation R&D Activities
    N. Larson [2017]
  • The Status of Spent Fuel Management
  • The Development Status of Spent Fuel Transportation & Storage Technology
  • Technical Basis for Storage of Zircalloy-Clad Spent Fuel in Inert Gases
  • Technical Bases for Extended Dry Storage of Spent Nuclear Fuel
  • Survey of Wet and Dry Spent Fuel Storage
  • Summary of the July 29, 2015 Public Meeting on Retrievability of Spent Fuel at an Independent Spent Fuel Installation
    U.S. NRC [2015]
  • Stress corrosion cracking of stainless-steel canister for concrete cask storage of spent fuel
    J. Tani [2008]
  • Strategy for the Management and Disposal of Used Nuclear Fuel and High-level Radioactive Waste
    U.S. DOE [2013]
  • Strain and Microstructure Characterization of Austenitic Stainless Steel Weld HAZs
  • Storage of Spent Nuclear Fuel
  • Storage of Spent Fuel in NRC Approved Storage Casks at Power Reactor Sites
    U.S. NRC [1990]
  • Standard review plan for the review of safety analysis reports for nuclear power plants
    U.S. NRC [1980]
  • Standard Specification for Pipe, Steel, Black and Hot-Dipped, Zinc-Coated, Welded and Seamless
  • Standard Specification for High-Strength Low-Alloy Structural Steel
  • Standard Specification for Carbon-Steel Wire and Welded Wire Reinforcement, Plain and Deformed, for Concrete
  • Standard Specification for Carbon Structural Steel
  • Standard Review Plan for Spent Fuel Dry Storage Systems at a General License Facility
    U.S. NRC [2010]
  • Standard Review Plan for Spent Fuel Dry Storage Facilities
    U.S. NRC [2000]
  • Standard Review Plan for Renewal of Spent Fuel Dry Cask Storage System Licenses and Certificates of Compliance
    U.S. NRC [2011]
  • Standard Review Plan for Renewal of Specific Licenses and Certificates of Compliance for Dry Storage of Spent Nuclear Fuel
    U.S. NRC [2015]
  • Standard Practice for the Preparation of Substitute Ocean Water
  • Spent Nuclear Fuel, The fact is? Truthful answer
  • Spent Fuel Transportation Applications: Modelling of Spent-fuel Rod Transverse Tearing and Rod Breakage Resulting from Transportation Accidents
  • Spent Fuel Transportation Applications: Global Forces Acting on Spent Fuel Rods and Deformation Patterns Resulting from Transportation Accidents
  • Spent Fuel Transportation Applications: Fuel Rod Failure Evaluation under Simulated Cask Side Drop Conditions
  • Spent Fuel Project Office Interim Staff Guidance – 9, Revision 1, Storage of components Associated with Fuel Assemblies
  • Spent Fuel Project Office Interim Staff Guidance – 4, Revision 1, Cask Closure Weld Inspections
  • Spent Fuel Project Office Interim Staff Guidance – 17, Interim Storage of Greater Than Class C Waste
  • Spent Fuel Project Office Interim Staff Guidance – 15, Materials Evaluation
  • Spent Fuel Project Office Interim Staff Guidance – 10, Revision 1, Alternatives to the ASME code
  • Spent Fuel Performance Assessment and Research, Final Report of a Coordinated Research Project (SPAR-II)
  • Spent Fuel Performance Assessment and Research
  • Spent Fuel Performance Assessment and Research
  • Spent Fuel Cladding Integrity during Dry Storage
  • Retrievability, Cladding Integrity and Safe Handling of Spent Fuel at an Independent Spent Fuel Storage Installation and During Transportation
    U.S. NRC [2013]
  • Resolution of Licensing Process Expectations for Pressurized Water Reactor Fuel Assemblies Susceptible to Top Nozzle Stress Corrosion Cracking in Dry Cask Spent Fuel Storage and Transportation
    U.S. NRC [2013]
  • Recommended Temperature Limits for Dry Storage of Spent Light Water Zircaloy-Clad Fuel Rods in Inert Gas
    I.S. Levy [1987]
  • Project Plan for the Regulatory Program Review to Support Extended Storage and Transportation of Spent Nuclear Fuel
  • Preoperational Testing of an Independent Spent Fuel Storage Installations
  • Preliminary Shielding Analysis of the Concrete Cask for Spent Nuclear Fuel Under Dry Storage Conditions
  • Prediction of Fatigue Crack Initiation Life Based on Pit Growth
    Y. Kondo [1989]
  • Pitting Corrosion Inhibition of 316Stainless Steel in Phosphoric Acid-Chloride Solutions:Part II, AES Investigation
  • Pitting Corrosion Inhibition of 316Stainless Steel in Phosphoric Acid-Chloride Solutions:Part I, Potentiodynamic and Potentiostatic Polarization Studies
  • Operation of an Independent Spent Fuel Storage Installations
  • NRC, Division of Spent Fuel Storage and Transportation Interim Staff Guidance - 24, Revision 0, The Use of a Demonstration Program as a Surveillance Tool for Confirmation of Integrity for Continued Storage of High Burnup Fuel Beyond 20 Years
  • Memo to Laszlo Zsidai of Holtec International entitled: Analysis of SaltSmart™Samples from Holtec Test Run
    C.R. Bryan [2013]
  • Master Plan for High-Level Radiation Waste Management
  • Marine Atmosphere Corrosion Cracking of Austenitic Stainless Steels
    R.M. Kain [1990]
  • Managing Aging Processes in Storage (MAPS) Report, Extended Storage Collaboration Program Meeting
    J. Wise [2016]
  • License Renewal Request – Fourth Request For Additional information
    U.S. NRC [2014]
  • Initiation and Propagation of Stress Corrosion Cracking of Stainless Steel Canister for Concrete Cask Storage of Spent Nuclear Fuel
    J. Tani [2009]
  • Influence of Chloride Concentration on Stress Corrosion Cracking of Austenitic Stainless Steel in LiCl Solutions
  • Influence of Alloy Sulfur Content and Bulk Electrolyte Composition on Crevice Corrosion Initiation of Austenitic Stainless Steels
  • Identification and Prioritization of the Technical Information Needs Affecting Potential Regulation of Extended Storage and Transportation of Spent Nuclear Fuel
    U.S. NRC [2012]
  • Gap Analysis to Support Extended Storage of Used Nuclear Fuel Rev. 0
    B. Hanson [2012]
  • Further Analysis of Extended Storage of Spent Fuel (BEFAST-Ⅲ)
  • Finite Element Analysis of Weld Residual Stresses in Austenitic Stainless Steel Dry Cask Storage System Canisters
    J. Kusnick [2013]
  • Final Report: Characterization of Canister Mockup Weld Residual Stresses
    D.G. Enos [2016]
  • Failure Criteria for Zircaloy Cladding Using a Damage-based Metal/Hydride Mixture Model
  • External SCC of austenitic stainless steels in atmosphere containing sea salt particles
    T. Nakamura [1985]
  • Extended Storage of Spent Fuel (BEFAST-II)
  • Evaluation method of corrosion lifetime of conventional stainless steel canister under oceanic air environment
    A. Kosaki [2008]
  • Environmental Report –Materials Licenses
    U.S. NRC [2017]
  • Environmental Report – independent spent fuel storage installation (ISFSI) or monitored retrievable storage installation (MRS) license
    U.S. NRC [2017]
  • Effects of long term dry storage of spent fuel
    M. Peehs [1992]
  • Effects of Marine Environments on Stress Corrosion Cracking of Austenitic Stainless Steels
  • Effective Thermal Conductivity and Edge Configuration Model for Spent Fuel Assembly
  • Effect of Simulated Groundwater Chemistry on Stress Corrosion Cracking of Alloy 22
    K.T. Chiang [2007]
  • Effect of Deformation on SCC of Un-sensitized Stainless Steel
  • Division of Spent Fuel Storage and Transportation Interim Staff Guidance – ISG-18, Revision 1, The Design and Testing of Lid Welds on Austenitic Stainless Steel Canisters as the Confinement Boundary for Spent Fuel Storage
  • Division of Spent Fuel Storage and Transportation Interim Staff Guidance - 1, Revision 2, Classifying the condition of Spent Nuclear Fuel for Interim Storage and Transportation Based on Function
  • Division of Spent Fuel Management Interim Staff Guidance – 2, Revision 2, Fuel Retrievability in Spent Fuel Storage Applications
  • Development of a Metal/Hydride Mixture Model for Zircaloy Cladding with Mixed Hydride Structure
  • Design Criteria for an Independent Spent Fuel Storage Installation (Dry Storage Type)
  • Data Report on Corrosion Testing of Stainless Steel SNF Storage Canisters
    D.G. Enos [2013]
  • Corrosion of Wrought Stainless Steels
  • Corrosion engineering
  • Control of Degradation of Spent LWR Fuel During Dry Storage in An Inert Atmosphere
  • Computational Modelling of Bounding Conditions for Pit Size on Stainless Steel in Atmospheric Environments
    Z.Y. Chen [2010]
  • Classification of Transportation Packaging and Dry Spent Fuel Storage System Components According to Importance to Safety
  • Chloride-induced stress corrosion cracking of used nuclear fuel welded stainless steel canisters: a review
    Y. Xie [2015]
  • Chloride-Induced Stress Corrosion Cracking of Candidate Canister Materials in Air
    M. Mayuzumi [2003]
  • Chloride-Induced Stress Corrosion Cracking Potential In Dry-storage Canisters for Spent Nuclear Fuel Rev. 1A
  • Chloride Induced Stress Corrosion Cracking of Type 304 and 304L Stainless Steels in Air
    M. Mayuzumi [2003]
  • Calvert Cliffs Stainless Steel Dry Storage Canister Inspection
  • Calvert Cliffs Independent Spent Fuel Storage Installation Lead and Supplemental Canister Inspection Report
    U.S. NRC [2012]
  • CASKS (Computer Analysis of Storage Casks): A Microcomputer Based Analysis System of Storage Casks Design Review
  • Behaviour of Spent Fuel Assemblies During Extended Storage (BEFAST-I)
  • Atmospheric Stress Corrosion Cracking Susceptibility of Welded and Unwelded 304, 304L, and 316L Austenitic Stainless Steels Commonly Used for Dry Cask Storage Containers Exposed to Marine Environments
    U.S. NRC [2010]
  • Assessment of Stress Corrosion Cracking Susceptibility of 316 Stainless Steel in Different Disposal Environments
    K.T. Chiang [2011]
  • Assessment of Stress Corrosion Cracking Susceptibility for Austenitic Stainless Steels Exposed to Atmospheric Chloride and Non-Chloride Salts
    U.S. NRC [2014]
  • Analysis of Dust Samples Collected from Spent Nuclear Fuel Interim Storage Containers at Hope Creek, Delaware, and Diablo Canyon, California
    C.R. Bryan [2014]
  • An Investigation into the Actual Condition of External Stress Corrosion Cracking (ESCC)of Austenitic Stainless Steels
    T. Kawamoto [1988]
  • AWS D1.4/D1.4M, Structural Welding Code - Reinforcing Steel
  • AWS D1.1/D1.1M, Structural Welding Code - Steel
  • ANSI/AWS A2.4-98, Standard Symbols for Welding, Brazing and Nondestructive Examination
  • 10 CFR Part 72, Licensing requirements for the independent storage of spent nuclear fuel and highlevel radioactive waste, and reactor-related greater than Class C waste
  • 10 CFR Part 72, Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor-Related Greater than Class C Waste
  • 10 CFR Part 72, Licensing Requirements for the Independent Storage of Spent Nuclear Fuel and High-Level Radioactive Waste