References
- Y.C. Jeong, "The Status of Spent Fuel Management", Winter School on Topical Issues, Kyung Hee university, Republic of Korea (2015).
- B.I. Choi, "The Development Status of Spent Fuel Transportation & Storage Technology", Winter School on Topical Issues, Kyung Hee university, Republic of Korea (2015).
- U.S. NRC, 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 (2018).
- U.S. NRC, 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 (2007).
- U.S. NRC, Division of Spent Fuel Management Interim Staff Guidance - 2, Revision 2, Fuel Retrievability in Spent Fuel Storage Applications (2016).
- U.S. NRC, Spent Fuel Project Office Interim Staff Guidance - 4, Revision 1, Cask Closure Weld Inspections (2016).
- U.S. NRC, Spent Fuel Project Office Interim Staff Guidance - 9, Revision 1, Storage of components Associated with Fuel Assemblies (2002).
- U.S. NRC, Spent Fuel Project Office Interim Staff Guidance - 10, Revision 1, Alternatives to the ASME code (2000).
- U.S. NRC, Spent Fuel Project Office Interim Staff Guidance - 15, Materials Evaluation (2001).
- U.S. NRC, Spent Fuel Project Office Interim Staff Guidance - 17, Interim Storage of Greater Than Class C Waste (2001).
- I.S. Levy, B.A. Chin, E.P. Simonen, C.E. Beyer, E.R. Gilbert, and A.B. Johnson, "Recommended Temperature Limits for Dry Storage of Spent Light Water Zircaloy- Clad Fuel Rods in Inert Gas", PNL-6189 (1987).
- A.B. Johnson and E.R. Gilbert, "Technical Basis for Storage of Zircalloy-Clad Spent Fuel in Inert Gases", Pacific Northwest Lab., PNL-4835 (1983).
- R.D. Manteufel and N.E. Todreas, "Effective Thermal Conductivity and Edge Configuration Model for Spent Fuel Assembly", Nuclear Technology, 105(3), 421-440 (1994). https://doi.org/10.13182/NT94-A34941
- U.S. NRC, 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 (2008).
- U.S. 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 (2014).
- U.S. NRC, "Standard Review Plan for Spent Fuel Dry Storage Systems at a General License Facility", NUREG-1536, Rev. 1 (2010).
- U.S. NRC, 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 (2007).
- U.S. NRC, 10 CFR Part 72, Licensing Requirements for the Independent Storage of Spent Nuclear Fuel and High-Level Radioactive Waste (1988).
- U.S. NRC, "Storage of Spent Fuel in NRC Approved Storage Casks at Power Reactor Sites", 55 FR 29181, Washington, DC (1990).
- U.S. NRC, "Retrievability, Cladding Integrity and Safe Handling of Spent Fuel at an Independent Spent Fuel Storage Installation and During Transportation", 78 FR 3853, Washington, DC (2013).
- U.S. NRC, "Summary of the July 29, 2015 Public Meeting on Retrievability of Spent Fuel at an Independent Spent Fuel Installation", ADAMS Accession No. ML15216A272 (2015).
- International Atomic Energy Agency, "Storage of Spent Nuclear Fuel", IAEA Safety Standards Series No. SSG-15 (2012).
- U.S. NRC, "Standard Review Plan for Spent Fuel Dry Storage Facilities", NUREG-1567 (2000).
- U.S. NRC, "Preoperational Testing of an Independent Spent Fuel Storage Installations", ADAMS Accession No. ML073100468, Washington, DC (2008).
- U.S. NRC, "Operation of an Independent Spent Fuel Storage Installations", ADAMS Accession No. ML073100489, Washington, DC (2008).
- U.S. NRC, "Project Plan for the Regulatory Program Review to Support Extended Storage and Transportation of Spent Nuclear Fuel", ADAMS Accession No. ML101390216, Washington, DC (2010).
- U.S. NRC, "Standard Review Plan for Renewal of Spent Fuel Dry Cask Storage System Licenses and Certificates of Compliance", NUREG-1927 (2011).
- U.S. NRC, "Standard Review Plan for Renewal of Specific Licenses and Certificates of Compliance for Dry Storage of Spent Nuclear Fuel", Draft NUREG-1927, Rev. 1. ADAMS Accession No. ML15068A331, Washington, DC (2015).
- J. Wise, "Managing Aging Processes in Storage (MAPS) Report", Extended Storage Collaboration Program Meeting, Charlotte, NC (2016).
- American Nuclear Society, "Design Criteria for an Independent Spent Fuel Storage Installation (Dry Storage Type)", ANSI/ANS-57.9 (1984).
- J.W. McConnell, A.L. Ayers, and M.J. Tyacke, "Classification of Transportation Packaging and Dry Spent Fuel Storage System Components According to Importance to Safety", U.S. NRC, NUREG/CR-6407 (1996).
- Lawrence Livermore National Laboratory, "CASKS (Computer Analysis of Storage Casks): A Microcomputer Based Analysis System of Storage Casks Design Review", U.S. NRC, NUREG/CR-6242 (1995).
- M.W. Schwartz and M.C. Witte, "Spent Fuel Cladding Integrity during Dry Storage", Lawrence Livermore National Laboratory, UCID-21181 (1987).
- Electric Power Research Institute, "Technical Bases for Extended Dry Storage of Spent Nuclear Fuel", 1003416, Palo Alto, CA (2002).
- B. Hanson, H. Alsaed, C. Stockman, D. Enos, R. Meyer, and K. Sorenson, "Gap Analysis to Support Extended Storage of Used Nuclear Fuel Rev. 0", FCRDUSED- 2011-000136, PNNL-20509 (2012).
- International Atomic Energy Agency, "Spent Fuel Performance Assessment and Research", IAEA-TECDOC- 1771, Vienna (2015).
- M.E. Cunningham, E.P. Simonen, R.T. Allemann, I.S. Levy, R.F. Hazelton, and E.R. Gilbert, "Control of Degradation of Spent LWR Fuel During Dry Storage in An Inert Atmosphere", PNL-6364 (1987).
- International Atomic Energy Agency, "Spent Fuel Performance Assessment and Research", IAEA-TECDOC- 1343, Vienna (2003).
- International Atomic Energy Agency, "Spent Fuel Performance Assessment and Research", Final Report of a Coordinated Research Project (SPAR-II), IAEATECDOC- 1680, Vienna (2012).
- International Atomic Energy Agency, "Behaviour of Spent Fuel Assemblies During Extended Storage (BEFAST- I)", IAEA-TECDOC-414, Vienna (1987).
- International Atomic Energy Agency, "Extended Storage of Spent Fuel (BEFAST-II)", IAEA-TECDOC- 673, Vienna (1992).
- International Atomic Energy Agency, "Further Analysis of Extended Storage of Spent Fuel (BEFAST-III)", IAEA-TECDOC-944, Vienna (1997).
- Electric Power Research Institute, "Development of a Metal/Hydride Mixture Model for Zircaloy Cladding with Mixed Hydride Structure", 1009694, Palo Alto, CA (2004).
- U.S. DOE, "Strategy for the Management and Disposal of Used Nuclear Fuel and High-level Radioactive Waste", Washington, DC (2013).
- U.S. NRC, "Identification and Prioritization of the Technical Information Needs Affecting Potential Regulation of Extended Storage and Transportation of Spent Nuclear Fuel", Washington, DC (2012).
- U.S. NRC, "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", Washington, DC (2013).
- International Atomic Energy Agency, "Survey of Wet and Dry Spent Fuel Storage", IAEA-TECDOC-1100, Vienna (1999).
- M. Peehs and K. Einfeld, "Effects of long term dry storage of spent fuel", Proc. of IHLRWM 1992", 1181-1187, American Nuclear Society, Las Vegas, NV (1992).
- Electric Power Research Institute, "Failure Criteria for Zircaloy Cladding Using a Damage-based Metal/Hydride Mixture Model", 1009693, Palo Alto, CA (2004).
- Electric Power Research Institute, "Spent Fuel Transportation Applications: Fuel Rod Failure Evaluation under Simulated Cask Side Drop Conditions", 1009929, Palo Alto, CA (2005).
- Electric Power Research Institute, "Spent Fuel Transportation Applications: Global Forces Acting on Spent Fuel Rods and Deformation Patterns Resulting from Transportation Accidents", 1011817, Palo Alto, CA (2005).
- Electric Power Research Institute, "Spent Fuel Transportation Applications: Modelling of Spent-fuel Rod Transverse Tearing and Rod Breakage Resulting from Transportation Accidents", 1013447, Palo Alto, CA (2006).
- U.S. NRC, "Assessment of Stress Corrosion Cracking Susceptibility for Austenitic Stainless Steels Exposed to Atmospheric Chloride and Non-Chloride Salts", NUREG/CR-7170 (2014).
- U.S. NRC, "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", NUREG/CR-7030 (2010).
- U.S. Nuclear Waste Technical Review Board, "Chloride- Induced Stress Corrosion Cracking Potential In Dry-storage Canisters for Spent Nuclear Fuel Rev. 1A", U.S. NWTRB (2017).
- Electric Power Research Institute, 1011820, "Effects of Marine Environments on Stress Corrosion Cracking of Austenitic Stainless Steels", Palo Alto, CA (2006).
- Electric Power Research Institute, 1025209, "Calvert Cliffs Stainless Steel Dry Storage Canister Inspection", Palo Alto, CA (2014).
- J. Kusnick, M. Benson, and S. Lyons, "Finite Element Analysis of Weld Residual Stresses in Austenitic Stainless Steel Dry Cask Storage System Canisters", U.S. NRC Technical Letter Report, ML13330A512 (2013).
- U.S. NRC, 10 CFR 51.60, Environmental Report - Materials Licenses (2017).
- U.S. NRC, 10 CFR 51.61, Environmental Report - independent spent fuel storage installation (ISFSI) or monitored retrievable storage installation (MRS) license (2017).
- U.S. NRC, "Standard review plan for the review of safety analysis reports for nuclear power plants", NUREG-75/087 (1980).
- C. Bryan, R. Dingreville, and D. Enos, "Weld Residual Stress Final Results and CISCC Model Development", Extended Storage Collaboration Program Meeting, Charlotte, NC (2016).
- N. Larson, "U.S. DOE Spent Nuclear Fuel Storage & Transportation R&D Activities", ESCP Fall Meeting, Charlotte, NC (2017).
- J. Tani, M. Mayuzumi, and N. Hara, "Initiation and Propagation of Stress Corrosion Cracking of Stainless Steel Canister for Concrete Cask Storage of Spent Nuclear Fuel", Corrosion, 65(3), 187-194 (2009). https://doi.org/10.5006/1.3319127
- J. Tani, M. Mayuzumi, and N. Hara, "Stress corrosion cracking of stainless-steel canister for concrete cask storage of spent fuel", J. Nucl. Mater., 379(1-3), 42-47 (2008). https://doi.org/10.1016/j.jnucmat.2008.06.005
- A. Kosaki, "Evaluation method of corrosion lifetime of conventional stainless steel canister under oceanic air environment", Nuclear Engineering and Design, 238(5), 1233-1240 (2008). https://doi.org/10.1016/j.nucengdes.2007.03.040
- R. L. Shamakian, A. R. Troiano, and R. F. Hehemann, "Influence of Chloride Concentration on Stress Corrosion Cracking of Austenitic Stainless Steel in LiCl Solutions", Corrosion, 36(6), 279-284 (1980). https://doi.org/10.5006/0010-9312-36.6.279
- M. Mayuzumi, T. Arai, and J. Tani, "Chloride-Induced Stress Corrosion Cracking of Candidate Canister Materials in Air", Proc. 13th APCCC, Osaka University, Japan (2003).
- G.S. Chae, K.W. Shin, B.M. Park, J.H. Han, G.H. Lee, and J.S. Park, "Preliminary Design of the Forced Gas Drying System for Spent Nuclear Fuel Dry Storage", J. Nucl. Fuel Cycle Waste Technol., 15(4), 403-409 (2017). https://doi.org/10.7733/jnfcwt.2017.15.4.403
- T.M. Kim, H.S. Dho, C.H. Cho, and J.H. Ko, "Preliminary Shielding Analysis of the Concrete Cask for Spent Nuclear Fuel Under Dry Storage Conditions", J. Nucl. Fuel Cycle Waste Technol., 15(4), 391-402 (2017). https://doi.org/10.7733/jnfcwt.2017.15.4.391
- C.Y. Baeg and C.H. Cho, "Development of the Vacuum Drying Process for the PWR Spent Nuclear Fuel Dry Storage", J. Nucl. Fuel Cycle Waste Technol., 14(4), 435-443 (2016). https://doi.org/10.7733/jnfcwt.2016.14.4.435
- C.Y. Baeg and C.H. Cho, "Status Analysis for the Confinement Monitoring Technology of PWR Spent Nuclear Fuel Dry Storage System", J. Nucl. Fuel Cycle Waste Technol., 14(1), 35-44 (2016). https://doi.org/10.7733/jnfcwt.2016.14.1.35
- D.H. Kim, K.S. Seo, J.C. Lee, C.H. Cho, H.K. Jang, and B.I. Choi, "A Test for Verifying a Tip-Over Analysis of a Dry Storage Cask", J. Nucl. Fuel Cycle Waste Technol., 4(3), 245-253 (2006).
- D.H. Kim, K.S. Seo, J.C. Lee, Y.D. Lee, C.H. Cho, and D.G. Lee, "A Test for Verifying a Tip-Over Analysis of a Dry Storage Cask", J. Nucl. Fuel Cycle Waste Technol., 4(2), 139-152 (2006).
- R.M. Kain, "Marine Atmosphere Corrosion Cracking of Austenitic Stainless Steels", Materials Performance, 29(12), 60-62 (1990).
- D.G. Enos, C.R. Bryan, and K.M. Norman, "Data Report on Corrosion Testing of Stainless Steel SNF Storage Canisters", FCRD-UFD-2013-000324, SAND2013-8314 (2013).
- C.R. Bryan and D.G. Enos, "Analysis of Dust Samples Collected from Spent Nuclear Fuel Interim Storage Containers at Hope Creek, Delaware, and Diablo Canyon, California", SAND2014-16383, Sandia National Laboratories, Albuquerque, NM (2014).
- U.S. NRC, "Calvert Cliffs Independent Spent Fuel Storage Installation Lead and Supplemental Canister Inspection Report", TAC No. L24475, ADAMS ML12212A216, Washington, DC (2012).
- U.S. NRC, "License Renewal Request - Fourth Request For Additional information", TAC No. L24475, ADAMS ML13170A574, Washington, DC (2014).
-
C.R. Bryan and D.G. Enos, "Memo to Laszlo Zsidai of Holtec International entitled: Analysis of SaltSmart
$^{TM}$ Samples from Holtec Test Run", SAND2013-9948P, Sandia National Laboratories, Albuquerque, NM (2013). - M.G. Fontana, Corrosion Engineering, 3rd ed., 12-152, McGraw-Hill, Singapore (1987).
- Z.Y. Chen and R.G. Kelly, "Computational Modelling of Bounding Conditions for Pit Size on Stainless Steel in Atmospheric Environments", J. Electrochem. Soc., 157(2), C69-C78 (2010). https://doi.org/10.1149/1.3261803
- Y. Kondo, "Prediction of Fatigue Crack Initiation Life Based on Pit Growth", Corrosion, 45(1), 7-11 (1989). https://doi.org/10.5006/1.3577891
- D.G. Enos and C.R. Bryan, "Final Report: Characterization of Canister Mockup Weld Residual Stresses", FCRD-UFD-2016-000064, SAND2016-12375R (2016).
- Y. Xie and J. Zhang, "Chloride-induced stress corrosion cracking of used nuclear fuel welded stainless steel canisters: A review", J. Nucl. Mater., 466, 85-93 (2015). https://doi.org/10.1016/j.jnucmat.2015.07.043
- American Society for Testing and Materials, "Standard Practice for the Preparation of Substitute Ocean Water", ASTM D1141-98, ASTM International, West Conshohocken, PA (2008).
- H.A. El Dahan, "Pitting Corrosion Inhibition of 316 Stainless Steel in Phosphoric Acid-Chloride Solutions: Part I, Potentiodynamic and Potentiostatic Polarization Studies", J. Mater. Sci., 34(4), 851-857 (1999). https://doi.org/10.1023/A:1004545501971
- H.A. El Dahan, "Pitting Corrosion Inhibition of 316 Stainless Steel in Phosphoric Acid-Chloride Solutions: Part II, AES Investigation", J. Mater. Sci., 34(4), 859- 868 (1999). https://doi.org/10.1023/A:1004597518809
- C.S. Brossia and R.G. Kelly, "Influence of Alloy Sulfur Content and Bulk Electrolyte Composition on Crevice Corrosion Initiation of Austenitic Stainless Steels", Corrosion, 54(2), 145-154 (1998). https://doi.org/10.5006/1.3284838
- K.T. Chiang, D.S. Dunn, and G.A. Cragnolino, "Effect of Simulated Groundwater Chemistry on Stress Corrosion Cracking of Alloy 22", Corrosion, 63(10), 940-950 (2007). https://doi.org/10.5006/1.3278312
- J.F. Grubb, T. DeBold, and J.D. Fritz, "Corrosion of Wrought Stainless Steels", Corrosion: Materials, 13B, ASM International, Materials Park, Ohio, USA (2005).
- T. Kawamoto, "An Investigation into the Actual Condition of External Stress Corrosion Cracking (ESCC) of Austenitic Stainless Steels", Zairyo-to-Kankyo, 37(1), 30-33 (1988).
- T. Nakamura, K. Yamamoto, and N. Kagawa, "External SCC of austenitic stainless steels in atmosphere containing sea salt particles", Zairyo-to-Kankyo, 34(6), 346-354 (1985).
- M. Mayuzumi, T. Arai, and K. Hide, "Chloride Induced Stress Corrosion Cracking of Type 304 and 304L Stainless Steels in Air", Zairyo-to-Kankyo, 52(3), 166-170 (2003). https://doi.org/10.3323/jcorr1991.52.166
- American Society for Testing and Materials, "Standard Specification for Carbon Structural Steel", ASTM A36/A36M-05, ASTM International, West Conshohocken, PA (2005).
- American Society for Testing and Materials, "Standard Specification for Pipe, Steel, Black and Hot-Dipped, Zinc-Coated, Welded and Seamless", ASTM A53/ A53M-00, ASTM International, West Conshohocken, PA (2001).
- American Society for Testing and Materials, "Standard Specification for Carbon-Steel Wire and Welded Wire Reinforcement, Plain and Deformed, for Concrete", ASTM A1064/A1064M-17, ASTM International, West Conshohocken, PA (2017).
- American Society for Testing and Materials, "Standard Specification for High-Strength Low-Alloy Structural Steel", ASTM A242/A242M-13, ASTM International, West Conshohocken, PA (2018).
- ANSI/AWS A2.4-98, Standard Symbols for Welding, Brazing and Nondestructive Examination, AWS, Miami, FL (2007).
- AWS D1.1/D1.1M, Structural Welding Code - Steel, AWS, Miami, FL (2015).
- AWS D1.4/D1.4M, Structural Welding Code - Reinforcing Steel, AWS, Miami, FL (2011).
- T.M. Angeliu, P.L. Andresen, E.L. Hall, J.A. Sutliff, and S. Sitzman, "Strain and Microstructure Characterization of Austenitic Stainless Steel Weld HAZs", Presentation at Corrosion 2000, 26-31 March, Orlando, Florida (2000).
- P.L. Andresen, T.M. Angeliu, W.R. Catlin, L.M. Young, and R.M. Horn, "Effect of Deformation on SCC of Un-sensitized Stainless Steel", Presentation at Corrosion 2000, 26-31 March, Orlando, Florida (2000).
- K.T. Chiang and P.K. Shukla, "Assessment of Stress Corrosion Cracking Susceptibility of 316 Stainless Steel in Different Disposal Environments", Proceedings of the 13th International High-Level Radioactive Waste Management Conference, Albuquerque, New Mexico (2011).
- J.S. Song, "Spent Nuclear Fuel, The fact is? Truthful answer", SNU Nuclear Energy Policy Center, Republic of Korea (2018).
- Ministry of Trade and Industry, "Master Plan for High-Level Radiation Waste Management", MTI, Republic of Korea (2016).