참고문헌
- U. S. Code of Federal Regulations, Title 10, Energy, Parts 0 to 50, Revised January 1, 1997, U.S. Government Printing Office, Washington, DC, 1997
- C. Grandjean et al., 'Oxidation and Quenching Experiments with High Burnup Cladding under LOCA Conditions,' Proc. 26th Water Reactor Safety Information Meeting, Bethesda, USA, October 26-28, 1998
- F. Nagase et al., 'Experiments on High Burnup Fuel Behavior under LOCA Conditions at JAERI,' Proc. ANS Topical Meeting on LWR fuel Performance, Park City, USA, April 10-13, 2000
- Y. Yan, T. Burtseva, and M. C. Billone, 'LOCA Results for Advanced-Alloy and High-Burnup Zircaloy Cladding,' Proc. Nuclear Safety Research Conference, October 21-24, 2003, Washington, DC.
- H. M. Chung, 'The Effects of Aliovalent Elements on Nodular Oxidation of Zr-Base Alloys,' Proc. Nuclear Safety Research Conference, October 21-24, 2003, Washington, DC.
- L. Portier, T. Bredel, J.C. Brachet, V. Maillot, J.P. Mardon, and A. Lesbos, 'Influence of Long-Service Exposures on the Thermal-Mechanical Behavior of Zry-4 and M5 Alloys in LOCA Conditions,' Proc. 14th Intl. Symp. On Zirconium in the Nuclear Industry, June 13-17, 2004, Stockholm, Sweden
- F. Nagase and T. Fuketa, 'Results from Studies on High Burnup Fuel Behavior under LOCA Conditions,' Proc. Nuclear Safety Research Conference, October 25-27, 2004, Washington, DC
- Y. Yan, T. A. Burtseva, and M. C. Billone, 'LOCA Integral Test Results for High-Burnup BWR Fuel,' Proc. Nuclear Safety Research Conference, October 25-27, 2004, Washington, DC
- M. C. Billone, Y. Yan, and T. A. Burtseva, 'Post-Quench Ductility of Advance Alloy Cladding,' Proc. Nuclear Safety Research Conference, October 25-27, 2004, Washington, DC
- J.C. Brachet, L. Portier, V. Maillot, T. Forgeron, J.P. Mardon, P. Jacques, A. Lesbros, 'Overview of the CEA Data on the Influence of Hydrogen on the Metallurgical and Thermalmechanical Behavior of Zircaloy-4 and M5 Alloys under LOCA Conditions,' Proc. Nuclear Safety Research Conference, October 25-27, 2004, Washington, DC
- E. Kolstad, W. Wiesenack, and V. Grismanovs, 'LOCA Testing at Halden,' Proc. Nuclear Safety Research Conference, October 25-27, 2004, Washington, DC
- L. Yegorova, K. Lioutov, N. Jouravkova, A. Konobeev, V. Smirnov, V. Chesanov, and A. Goryachev, 'Experimental Study of Embrittlement of Zr-1%Nb VVER Cladding under LOCA-Relevant Conditions,' NUREG/IA-0211, IRSN-194, NSI RRC KI 3188, U.S. Nuclear Regulatory Commission, March 2005
- Report of Advisory Task Force on Power Reactor Emergency Cooling, TID-24226, 1967
- General Design Criteria for Nuclear Power Plants, U.S. Code of Federal Regulations, Title 10, Part 50, Appendix A, February 20, 1971, amended
- Interim Acceptance Criteria for Emergency Core-Cooling Systems for Light-Water Power Reactors, U.S. Federal Register 36 (125), pp. 12247-12250, June 29, 1971
- W.B. Cottrell, 'ECCS Rule-Making Hearing,' Nucl. Safety 15 (1974) 30-55
- New Acceptance Criteria for Emergency Core-Cooling Systems of Light-Water-Cooled Nuclear Power Reactors, Nucl. Safety 15 (1974) 173-184
- Atomic Energy Commission Rule-Making Hearing, Opinion of the Commission, Docket RM-50-1, December 28, 1973
- J. C. Hesson et al., 'Laboratory Simulations of Cladding-Steam Reactions Following Loss-of-Coolant Accidents in Water-Cooled Power Reactors,' ANL-7609, Argonne National Laboratory, January 1970
- G. W. Parker et al., 'Release of Fission Products from Reactor Fuels during Transient Accidents Simulated in TREAT,' Proc. Intl. Symp. Fission Product Release and Transport under Accident Conditions, Oak Ridge, TN, April 5-7,1965
- T. Fujishiro et al., 'Light Water Reactor Fuel Response during Reactivity Initiated Accident Experiments,' NUREG/CR-0269, August 1978
- H. M. Chung and T. F. Kassner, 'Pseudobinary Zircaloy-Oxygen Phase Diagram,' J. Nucl. Mater. 84 (1979) 327-339 https://doi.org/10.1016/0022-3115(79)90172-7
- H. M. Chung and T. F. Kassner, 'Embrittlement Criteria for Zircaloy Fuel Cladding Applicable to Accident Situations in Light-Water Reactors,' NUREG/CR-1344, ANL-79-48, Argonne National Laboratory, January 1980
- Parsons, P.D. et al., 'The Deformation, Oxidation and Embrittlement of PWR Fuel Cladding in a Loss-of-Coolant Accident: A State-of-the-Art Report,' CSNI Report 129, December 1986
- Zuzek, E. et al., 'The H-Zr (Hydrogen-Zirconium) System,' Bulletin of Alloy Phase Diagrams, 11 (1990) 385-395 https://doi.org/10.1007/BF02843318
- Atomic Energy Commission Rule-Making Hearing, Supplemental Testimony of the Regulatory Staff Docket RM-50-1, October 26, 1972
- Atomic Energy Commission Rule-Making Hearing, Concluding Statement of the Regulatory Staff, Docket RM-50-1, April 16, 1973
- D. O. Hobson and P. L. Rittenhouse, 'Embrittlement of Zircaloy Clad Fuel Rods by Steam During LOCA Transients,' ORNL-4758, Oak Ridge National Laboratory, January 1972
- D. O. Hobson, 'Ductile-brittle behavior of Zircaloy fuel cladding,' Proc. ANS Topical Mtg. on Water Reactor Safety, Salt Lake City, March 26, 1973, pp. 274-288
- L. Baker and L. C. Just, 'Studies of Metal-Water Reactions at High Temperatures, III. Experimental and Theoretical Studies of the Zirconium-Water Reaction,' ANL-6548, Argonne National Laboratory, May 1962
- R. E. Pawel, 'Oxygen Diffusion in Beta Zircaloy during Steam Oxidation,' J. Nucl. Mater. 50 (1974) 247-258 https://doi.org/10.1016/0022-3115(74)90095-6
- J. V. Cathcart, R. E. Pawel, R. A. McKee, R. E. Durscel, G. J. Yurek, J. J. Campbell, and S. H. Jury, 'Zirconium Metal-Water Oxidation Kinetics IV, Reaction Rate Studies, ORNL/NUREG-17, August 1977
- J. D. Duncan and J. E. Leonard, Thermal Response and Cladding Performance of Zircaloy Clad Simulated Fuel Bundles Under High Temperature Loss of Coolant Conditions, GEAP-13174, General Electric Company (May 1971)
- G. J. Scatena, 'Fuel Cladding Embrittlement during a Loss of Coolant Accident,' NEDO-10674, General Electric Company, October 1972
- R. H. Meservey and R. Henzel, 'Embrittlement Behavior of Zircaloy in an Emergency Core Cooling Environment,' IN-1389, Idaho Nuclear Corporation, September, 1970
- H. Uetsuka et al., 'Failure-Bearing Capability of Oxidized Zircaloy-4 Cladding under Simulated Loss-of-Coolant Condition,' J. Nucl. Sci. Tech. 20 (1983) 941-950 https://doi.org/10.3327/jnst.20.941
- M. Reocreux and E. Scott de Martinville, 'A Study of Fuel Behavior in PWR Design Basis Accident: An Analysis of Results from the PHEBUS and EDGAR Experiments,' Nucl. Eng. Design 124 (1990) 363-378 https://doi.org/10.1016/0029-5493(90)90301-D
- M. Suzuki and S. Kawasaki, 'Development of Computer Code PRECIP-II for Calculation of Zr-Steam Reaction,' J. Nucl. Sci. Tech. 17 (1980) 291 https://doi.org/10.3327/jnst.17.291
- C. Grandjean et al., 'High Burnup UO2 Fuel LOCA Calculations to Evaluate the Possible Impact of Fuel Relocation after Burst,' ANL Program Review Meeting, Rockville (USA), October 22, 1999
- P. Hofmann et al., 'PECLOX: A Computer Model for the Calculation of the Internal and the External Zircaloy Cladding Oxidation,' KFK-4422 Part 2, October 1988
- A. Sawatzky, 'Proposed Criterion for the Oxygen Embrittlement of Zircaloy-4 Fuel Cladding,' Proc. 4th Symp. on Zirconium in the Nuclear Industry, Stratford-on-Avon, UK, June 27-29, 1978
- H. Uetsuka et al., 'Zircaloy-4 Cladding Embrittlement due to Inner Surface Oxidation under Simulated Loss-of-Coolant Condition,' J. Nucl. Sci. Tech. 18 (1981) 705-717 https://doi.org/10.3327/jnst.18.705
- H. Uetsuka, et al., 'Embrittlement of Zircaloy-4 due to Oxidation in Environment of Stagnant Steam,' J. Nucl. Sci. Tech. 19 (1982), 158-165 https://doi.org/10.3327/jnst.19.158
- K. Komatsu, 'The Effects of Oxidation Temperature and Slow Cooldown on Ductile-Brittle Behavior of Zircaloy Fuel Cladding,' Proc. CSNI Specialists' Meeting on the Behavior of Water Reactor Fuel Elements under Accident Conditions, Spaatind, Norway, September 13-16, 1976
- K. Komatsu et al., 'Load-Bearing Capability in Deformed and Oxidized Zircaloy Cladding,' Proc. CSNI Specialist Mtg. on Safety Aspects of Fuel Behavior in Off-Normal and Accident Conditions, Espoo, Finland, September 1-4, 1980
- R. A. Lorenz, 'Fuel Rod Failure under Loss-of-Coolant Conditions in TREAT,' Nucl. Tech. 11 (1971) 502-520 https://doi.org/10.13182/NT71-A30847
- F. M. Haggag, 'Zircaloy Cladding Embrittlement Criteria: Comparison of In-Pile and Out-of-Pile. Results,' NUREG/CR-2757, July 1982
- J. Boehmert, 'Embrittlement of Zr-Nbl at Room Temperature after High-Temperature Oxidation in Steam Atmosphere,' Kerntechnik 57 (1992) 55-58
- J. Boehmert, M. Dietrich, and J. Linek, 'Comparative Studies on High-Temperature Corrosion of ZrNbl and Zircaloy-4,' Nucl. Engr. Design 147 (1993) 53-62 https://doi.org/10.1016/0029-5493(94)90256-9
- A. Griger, L. Maroti, L. Matus, and P. Windberg, 'Ambient and High-Temperature Mechanical Properties of ZrNbl Cladding with Different Oxygen and Hydrogen Content,' Proc. Enlarged Halden Program Group Meeting, May 24-29, 1999, Loen, Norway
- L. Maroti, 'Ring-Compression Test Results and Experiments Supporting LOCA PCT, Oxidation and Channel Blockage Criteria,' Proc. OECD Topical Mtg. on LOCA Fuel Safety Criteria, March 22-23, 2001, Aix-en-Provence, France
- Yu. K. Bibilashvili, N. B. Sokolov, L. N. Andreeva-Andrievskaya, V. Yu. Tonkov, A. V. Salatov, A. M. Morosov, and V. P. Smirnov, 'Thermomechanical Properties of Oxidized Zirconium-Based Alloy Claddings in Loss of Coolant Accident Conditions,' Proc. OECD Topical Mtg. on LOCA Fuel Safety Criteria, March 22-23, 2001, Aix-en-Provence, France
- V. Vrtilkova, M. Valach, and L. Molin, 'Oxidation and Hydriding Properties of Zr-lNb Cladding Material in Comparison with Zircaloys,' Proc. IAEA Technical Committee Mtg. on Influence of Water Chemistry on Fuel Clad Behavior, October 4-8, 1993, Rez, Czech Republic; also in IAEA TECDOC-927, Vienna, 1997, pp. 227-251
- V. Asmolov, L. Yegorova, K. Lioutov, A. Konoveyev, V. Smirnov, A. Goryachev, V. Chesanov, and V. Prokhorov, 'Understanding LOCA-Related Ductility in E110 Cladding,' Proc. Nuclear Safety Research Conference, October 28-30, 2002, Washington, D.C.
- L. Yegorova and K. Lioutov, 'LOCA Behavior of E110 Alloy,' Proc. Nuclear Safety Research Conference, October 20-22, 2003, Washington, D.C.
- M. Billone, 'Overview of Advanced Alloy Post-Quench Ductility Program,' Review Mtg. of LOCA and Dry-Cask-Storage Programs, July 16-17, 2003, Argonne, Illinois
- Y. Yan, T. Burtseva, and M. Billone, 'LOCA Results for Advanced-Alloy and High-Burnup Zircaloy Cladding,' Proc. Nuclear Safety Research Conference, October 20-22, 2003, Washington, D.C.
-
J.-C. Brachet, J. Pelchat, D. Harmon, R. Maury, P. Jacques, and J.-P. Mardon, 'Mechanical Behavior at Room Temperature and Metallurgical Study of Low-Tin Zry-4 and M5 Alloys after Oxidation at
$1100^{\circ}C$ and Quenching,' Proc. IAEA Technical Committee Mtg. on Fuel Behavior under Transient and LOCA Conditions, September 10-14, 2001, Halden, Norway - W. J. Leach, 'Ductility Testing of Zircaloy-4 and Zirlo Cladding after High-Temperature Oxidation in Steam,' Proc. OECD Topical Mtg. on LOCA Fuel Safety Criteria, March 22-23, 2001, Aix-en-Provence, France
- C. Wagner, Naturwissenschaften, 31 (1943) 265 https://doi.org/10.1007/BF01475685
- K. Kiukkola and C. Wagner, J. Electrochem. Soc., 104 (1957) 379 https://doi.org/10.1149/1.2428586
- W. W. Stephens, 'Extractive Metallurgy of Zirconioum - 1945 to the Present,' Zirconium in the Nuclear Industry: Sixth International Conference, ASTM STP 824, D. G. Franklin and R. B. Adams, Eds., American Society for Testing and Materials, 1984, pp. 5-36
- L. Moulin, P. Thouvenin, and P. Brun, 'New Process for Zirconium and Hafnium Separation,' Zirconium in the Nuclear Industry: Sixth International Conference, ASTM STP 824, D. G. Franklin and R. B. Adams, Eds., American Society for Testing and Materials, 1984, pp. 37-44
- M. Takahashi, H. Miyazaki, and Y. Katoh, 'New Solvent Extraction Process for Zirconium and Hafnium,' Zirconium in the Nuclear Industry: Sixth International Conference, ASTM STP 824, D. G. Franklin and R. B. Adams, Eds., American Society for Testing and Materials, 1984, pp. 45-56
- P. Pint and S. N. Flengas, 'Production of Zirconium Metal by Fused-Salt Electrolysis,' Transactions, Institution of Mining and Metallurgy, London, Section C, Vol. 87, March 1978, pp. C29-C49
- N. P. Sajin and E. A. Pepelyaeva, 'Separation of Hafnium from Zirconium and Production of Pure Zirconium Dioxide,' Proc. Intl. Conf. on Peaceful Uses of Atomic Energy, Vol. 8, Presentation P/634, pp.559, August 8-20, 1955, Geneva, Switzerland
- K. Shimizu, K. Kobayashi, G. E. Thompson, P. Skeldon, and G. C. Wood, J. Electrochem. Soc. 144 (1997) 418 https://doi.org/10.1149/1.1837425
- R. F. Welton, private communication, November 2003; also see: 'Target Material Characterization Apparatus and Measurement Techniques,' presentation slides available in website of Holifield Radioactive Ion Beam Facility, Beam Development - Target Material Characterization Laboratory, Physics Division, Oak Ridge National Laboratory, 2003
- The Handbook of Binary Phase Diagrams, W. G. Moffatt, Genium Publishing Corporation, Schenectady, NY, 1984
- C. T. Ward, D. L. Mathis, and R. W. Staehle, Corrosion 25 (1969) 394 https://doi.org/10.5006/0010-9312-25.9.394
- P. E. C. Bryant and P. R. Habicht, Combustion Engineering Internal Report TIS-5065, also in Proc. IAEA Workshop on Stress Corrosion Cracking, March 29-31,1976
- M. Takemoto, T. Shonohara, M. Shirai, and T. Shinogaya, Mater. Performance 24 (1985) 26
- H. M. Chung, W. E. Ruther, J.-H. Park, J. E. Sanecki, and N. J. Zaluzec, Paper #443, Corrosion '99, San Antonio, Texas, April 25-30, 1999
- H. M. Chung, J.-H. Park, J. E. Sanecki, N. J. Zaluzec, T. T. Yang, and M. S. Yu, 'Cracking Mechanism of Type 304L Stainless Steel Core Shroud Welds,' Proc. 9th Intnl. Conf. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, Eds. S. Bruemmer, P. Ford, and G. Was, The Minerals, Metals, and Materials Society, Warrendale, PA, 1999, pp. 973-984
- L. Portier, T. Bredel, J. C. Brachet, V. Maillot, J. P. Mardon, and A. Lesbos, 'Influence of Long Service Exposures on the Thermal-Mechanical Behavior of Zry-4 and M5TM Alloys in LOCA Conditions,' presented at the 14th International Symposium on Zirconium in the Nuclear Industry, Stockholm, Sweden, June 13-17, 2004, to be published in meeting proceedings
- M. C. Billone, 'LOCA Embrittlement Correlation,' Argonne National Laboratory Interim Report, April 8, 2005
- V. Vrtilkova, L. Novotny, R. Doucha, and J. Vesely, 'An Approach to the Alternative LOCA Embrittlement Criterion,' Proc. of Meeting of OECD Nuclear Energy Agency Committee on the Safety of Nuclear Installations Special Expert Group on Fuel Safety Margins (SEGFSM), May 25-26, 2004, Argonne, Illinois, USA
- S. Malang, 'SIMTRAN-1: A Computer Code for Simultaneous Calculation of Oxygen Distribution and Temperature Profiles in Zircaloy during Exposure to High Temperature Oxidising Environment,' ORNL-5083, Oak Ridge National Laboratory, November 1975
- W. G. Dobson and R. R. Biederman, 'ZORO-1: A Finite Difference Computer Model for Zircaloy Oxidation in Steam,' EPRI-NP-347, Electric Power Research Institute, December 1976