A Case Study of the Susceptibility of Zircaloy-4 Sheathing to Iodine Stress-Corrosion Cracking as a Function of Their Metallurgical History in Fabrication — Oak Academic Publishing
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A Case Study of the Susceptibility of Zircaloy-4 Sheathing to Iodine Stress-Corrosion Cracking as a Function of Their Metallurgical History in Fabrication
Department of Chemical Engineering, Queen’s University, Kingston, Canada
,
Clean Core Thorium Energy, Inc., Chicago, IL, USA
,
Department of Chemistry and Chemical Engineering, Royal Military College of Canada, Kingston, Canada
,
Department of Mechanical and Aerospace Engineering, Royal Military College of Canada, Kingston, Canada
1 Department of Chemical Engineering, Queen’s University, Kingston, Canada
2 Clean Core Thorium Energy, Inc., Chicago, IL, USA
3 Department of Chemistry and Chemical Engineering, Royal Military College of Canada, Kingston, Canada
4 Department of Mechanical and Aerospace Engineering, Royal Military College of Canada, Kingston, Canada
This experimental undertaking has primarily focused on determining the dependency of Pellet-Cladding Mechanical Interaction (PCMI) conditions and the resulting Iodine Stress-Corrosion Cracking (ISCC) failures on residual stresses within a wide range of manufactured CANDU Zircaloy-4 cladding (sheathing). ISCC failures remain a fuel performance concern for water-cooled reactors, including CANDU reactors, accommodating a multitude of power maneuverability events, at high discharge burnups. A multi-year examination of more recent and vintage Zircaloy-4 sheathing samples and their associated post-production stress state from two independent sources is provided. A relationship between the residual stress history in manufacturing processes of Zircaloy-4 and ISCC has been investigated, by static loading of slotted ring samples in iodine-methanol solutions (10 g·L − 1 ) at room temperature. Results indicate that inherent residual tensile stress state of the sheathing above a certain threshold is strongly correlated to the failure in ISCC process.
Robertson, J.A.L. (1975) Proceedings of the Joint Topical Meeting on Commercial Nuclear Fuel Technology Today, Toronto, 28-30 April, 2.
Rosenbaum, H.S., Davies, J.S. and Pon, J.Q. (1966) US Report GEQP-5100-5. https://www-pub.iaea.org/MTCD/Publications/PDF/te_1185_prn.pdf
International Atomic Energy Agency (2000) Iodine Induced Stress Corrosion Cracking of Zircaloy Fuel Cladding Materials, IAEA-TECDOC-1185, IAEA, VIENNA.
Cox, B. (1990) Pellet-Clad Interaction (PCI) Failures of Zirconium Alloy Fuel Cladding—A Review. Journal of Nuclear Materials , 172, 249-292. https://doi.org/10.1016/0022-3115(90)90282-r
Hellouin de Menibus, A., Auzoux, Q., Besson, J. and Crépin, J. (2014) Temperature Increase of Zircaloy-4 Cladding Tubes Due to Plastic Heat Dissipation during Tensile Tests at 0.1-10 S-1 Strain Rates. Journal of Nuclear Materials , 454, 247-254. https://doi.org/10.1016/j.jnucmat.2014.08.011
Knaab, H., Gartner, M. and Sontheimer, F. (1987) Proceedings of the IAEA Meeting on Pellet-Cladding Interaction and Load-Following Behaviour of Water Reactor Fuel, Lyon, 18-21 May 1987, Report No. IWGFPT/28.
Piro, M.H.A., Sunderland, D., Livingstone, S., Sercombe, J., Revie, W., Quastel, A., Terrani, K. and Judge, C. (2017) A Review of Pellet-Clad Interaction Behavior in Zirconium Alloy Fuel Cladding. Ref. Modul. Mater. Sci. Mater. Eng, Elsevier.
Garzarolli, F., Manzel, R., Peehs, M. and Stehle, H. (1978) Kerntechnik , 20, 27-31.
van der Schaaf, B. (1974) Fracture of Zircaloy-2 in an Environment Containing Iodine. In: Zirconium in Nuclear Applications , ASTM International, 479-494. https://doi.org/10.1520/stp32135s
Cubicciotti, D., Jones, R. and Syrett, B. (1982) Chemical Aspects of Iodine-Induced Stress Corrosion Cracking of Zircaloys. In: Garde, A.M. and Bradley, E.R., Eds., Zirconium in the Nuclear Industry , ASTM International, 146-157. https://doi.org/10.1520/stp37052s
Peehs, M., Steinberg, E. and Stehle, H. (1980) Proceedings of the IAEA Meeting on Pellet-Cladding Interaction in Water Reactors, Risø, p. 169.
Kleykamp, H. (1985) The Chemical State of the Fission Products in Oxide Fuels. Journal of Nuclear Materials , 131, 221-246. https://doi.org/10.1016/0022-3115(85)90460-x
Wimmer, E., Najafabadi, R., Young Jr, G.A., Ballard, J.D., Angeliu, T.M., Vollmer, J., et al. (2010) Ab Initio Calculations for Industrial Materials Engineering: Successes and Challenges. Journal of Physics: Condensed Matter , 22, Article ID: 384215. https://doi.org/10.1088/0953-8984/22/38/384215
Davies, J.H., Rosenbaum, H.S., Armijo, J.S., Rosicky, E., Esch, E.L. and Wisner, S.B. (1977) Proceedings of the ANS Topical Meeting on Water Reactor Fuel Performance, ANS, St. Charles, p. 230.
Une, K. (1980) Threshold Values Characterising Iodine-Induced SCC of Zircaloys Obtained in Laboratory Experiments. Proceedings of the IAEA Meeting on Pellet - Cladding Interaction in Water Reactors , Risø, p. 226.
Nikulin, S.A. and Rozhnov, A.B. (2005) Corrosion Cracking of Zirconium Cladding Tubes (A Review). I. Methods of Study and Mechanisms of Fracture. Metal Science and Heat Treatment , 47, 71-79. https://doi.org/10.1007/s11041-005-0034-2
Sidky, P.S. (1998) Iodine Stress Corrosion Cracking of Zircaloy Reactor Cladding: Iodine Chemistry (A Review). Journal of Nuclear Materials , 256, 1-17. https://doi.org/10.1016/s0022-3115(98)00044-0
Schuster, I. and Lemaignan, C. (1992) Influence of Texture on Iodine-Induced Stress Corrosion Cracking of Zircaloy-4 Cladding Tubes. Journal of Nuclear Materials , 189, 157-166. https://doi.org/10.1016/0022-3115(92)90528-s
Linga Murty, K. and Charit, I. (2006) Texture Development and Anisotropic Deformation of Zircaloys. Progress in Nuclear Energy , 48, 325-359. https://doi.org/10.1016/j.pnucene.2005.09.011
Garlick, A. and Wolfenden, P.D. (1971) Fracture of Zirconium Alloys in Iodine Vapour. Journal of Nuclear Materials , 41, 274-292. https://doi.org/10.1016/0022-3115(71)90165-6
Withers, P.J. and Bhadeshia, H.K.D.H. (2001) Residual Stress. Part 2—Nature and Origins. Materials Science and Technology , 17, 366-375. https://doi.org/10.1179/026708301101510087
Noyan, I.C. and Cohen, J.B. (1987) Residual Stress: Measurement by Diffraction and Interpretation. Springer, 1-46.
Porrot, E., Charles, M., Lefebvre, F. and Lemaignan, C. (1988) Mechanisms of Cladding Deformation, Fission Gas Release during Power Transients at High Burnup. LWR Fuel Performance, Williamsburg.
Park, S.Y., Kim, J.H., Lee, M.H. and Jeong, Y.H. (2008) Stress-Corrosion Crack Initiation and Propagation Behavior of Zircaloy-4 Cladding under an Iodine Environment. Journal of Nuclear Materials , 372, 293-303. https://doi.org/10.1016/j.jnucmat.2007.03.258
Le Boulch, D., Fournier, L. and Catherine, C.S. (2004) Pellet-Clad Interaction in Water Reactor Fuels. Seminar Proceedings , Aix en Provence, 9-11 March 2004, p. 253. https://www.oecd.org/content/dam/oecd/en/publications/reports/2005/07/pellet-clad-interaction-in-water-reactor-fuels_g1gh5b9b/9789264011588-en.pdf
Rosenbaum, H.S. (1982) GEAP-25163-6. General Electric Company.
Garzarolli, F., von Jan, R. and Stehle, H. (1979) The Main Causes of Fuel Element Failure in Water-Cooled Power Reactors. Atomic Energy Review , 7, 31-128.
Videm, K. and Lunde, L. (1979) In: Papa-Zoglon, T.P., Ed., Zirconium in the Nuclear Industry , Four th Conference , ASTM STP 681, American Society for Testing and Materials, p. 234.
Mattas, R.F., Yaggee, F.L. and Neimark, L.A. (1982) In: Franklin, D.G., Ed., Zirconium in the Nuclear Industry , Fifth Conference , ASTM STP 754, American Society for Testing and Materials, 158.
Floyd, M. (2001) Proceedings of the Seventh CANDU Fuel Conference, Kingston, 1-20.
Gartner, M. and LaVake, J.C. (1983) Power Ramp Testing and Non-Destructive Post-Irradiation Examinations of High Burnup PWR Fuel Rods. Proceedings of the IAEA Meeting on Pellet - Cladding Interaction in Water Reactor Fuel , Seattle, p. 27.
Roberts, J.T.A. (1981) LWR Core Materials. In: Roberts, J.T.A., Ed., Structural Materials in Nuclear Power Systems , Springer, 53-136. https://doi.org/10.1007/978-1-4684-7194-6_2
Videm, K. and Lunde, L. (1977) Stress Corrosion Cracking of Zircaloy Fuel Cladding Tubes Under Power Ramps and in Laboratory Tests. American Nuclear Society.
Piro, M.H.A., Sunderland, D., Livingstone, S., Sercombe, J., Revie, W., Quastel, A., Terrani, K. and Judge, C. (2020) 2.09-Pellet-Clad Interaction Behavior in Zirconium Alloy Fuel Cladding. Comprehensive Nuclear Materials ( Second Edition ), 2, 248-306. https://doi.org/10.1016/B978-0-12-803581-8.09799-X
Floyd, M.R., Leach, D.A., Moeller, R.E., Elder, R.R., Chenier, R.J. and O’Brien, D. (1992) Behaviour of Bruce NGS-A Fuel Irradiated to a Burnup of ~500 MWh/kgU. Proce edings of the Third International Conference on CANDU Fuel , Pembroke, 1-16.
Lewis, B.J., Thompson, W.T., Kleczek, M.R., Shaheen, K., Juhas, M. and Iglesias, F.C. (2011) Modelling of Iodine-Induced Stress Corrosion Cracking in CANDU Fuel. Journal of Nuclear Materials , 408, 209-223. https://doi.org/10.1016/j.jnucmat.2010.10.063
Hastings, I.J., Tayal, M. and Manzer, A.M. (1990) CANDU Fuel Performance in Load-Following Operation. AECL-9812.
Erbacher, F., Neitzel, H., Rosinger, H., Schmidt, H. and Wiehr, K. (1982) Burst Criterion of Zircaloy Fuel Claddings in a Loss-Of-Coolant Accident. In: Garde, A.M. and Bradley, E.R., Eds., Zirconium in the Nuclear Industry , ASTM International, 271-283. https://doi.org/10.1520/stp37058s
Beguin, S. (2005) PCI-Related Constraints on EDF PWRs and Associated Challenges. In: Pellet-Clad Interact. Water React. Fuels, Organisation for Economic Co-Operation and Development, Nuclear Energy Agency, 75, Paris (France); 548 p; Worldcat; Jul 2005; p. 53-62; Seminar: Pellet-Clad Interaction in Water Reactor Fuels; Aix-en-Provence (France); 9-11 Mar 2004, 53-62.
Labrot, G. (1984) Une Ithaque pour immigrés, la gare de Porta Nova à Turin. Le Monde alpin et rhodanien. Revue régionale d ’ ethnologie , 12, 161-164. https://doi.org/10.3406/mar.1984.1254
Tasooji, A., Einziger, R. and Miller, A. (1984) Modeling of Zircaloy Stress-Corrosion Cracking: Texture Effects and Dry Storage Spent Fuel Behavior. In: Garde, A.M. and Bradley, E.R., Eds., Zirconium in the Nuclear Industry , ASTM International, 595-626. https://doi.org/10.1520/stp34497s
Schrire, D., Lysell, G., Grigoriev, V. and Josefsson, B. (2000) Proceedings of the IAEA Technical Committee Meeting on Fuel Chemistry and Pellet-Clad Interaction Related to High Burnup Fuel, Vienna, p. 105.
International Atomic Energy Agency (2019) Review of Fuel Failures in Water Cooled Reactors, An Update of IAEA Nuclear Energy Series No. NF-T-2.1. IAEA Vienna.
Ledergerber, G., Valizadeh, S., Wright, J., Limbäck, M., Hallstadius, L., Gavillet, D., et al. (2010) TopFuel, 513-524.
Yang, R., Cheng, B., Deshon, J., Edsinger, K. and Ozer, O. (2006) Fuel R&D to Improve Fuel Reliability. Journal of Nuclear Science and Technology , 43, 951-959. https://doi.org/10.3327/jnst.43.951
Birk, S. (2010) Antitrust Measures Support Quality Patient Care. Internal Medicine News , 43, 53. https://doi.org/10.1016/s1097-8690(10)70757-5
Joseph, J., Atabek, R. and Trotabas, M.L. (1982) The CEA-Fragema Ramp Test Programme for the Study of the Effect of Power Cycling on PCI at High Burn-Up. Proc eeding of Specialists MTG on Power Ramping , Cycling Behaviour of Water Reactor Fuels , Petten, p. 36.
Wood, J.C. (1972) Factors Affecting Stress Corrosion Cracking of Zircaloy in Iodine Vapour. Journal of Nuclear Materials , 45, 105-122. https://doi.org/10.1016/0022-3115(72)90178-x
Piro, M., Sunderland, D., Revie, W., Livingstone, S., Dimayuga, I., Douchant, A., et al. (2018) Potential Mitigation Strategies for Preventing Stress Corrosion Cracking Failures in High-Burnup Candu Fuel. CNL Nuclear Review , 7, 127-146. https://doi.org/10.12943/cnr.2016.00011
Miller, A.K., Ocken, H. and Tasooji, A. (1981) Iodine Stress Corrosion Cracking of Zircaloy: Laboratory Data, a Phenomenological Model, and Predictions of In-Reactor Behavior. Journal of Nuclear Materials , 99, 254-268. https://doi.org/10.1016/0022-3115(81)90194-x
Videm, K., Lunde, L., Hollowell, T., Vilpponen, K. and Vitanza, C. (1979) Cracking of Cladding Tubes Caused by Power Ramping and by Laboratory Stress Corrosion Experiments. Journal of Nuclear Materials , 87, 259-267. https://doi.org/10.1016/0022-3115(79)90562-2
Sejnoha, R. and Wood, J. (1979) Iodine-induced Stress Corrosion Cracking of Fixed Deflection Stressed Slotted Rings of Zircaloy Fuel Cladding. In: Garde, A.M. and Bradley, E.R., Eds., Zirconium in the Nuclear Industry , ASTM International, 261-284. https://doi.org/10.1520/stp36685s
Farahani, M., Chan, P.K., Corcoran, E.C., Hameed, R. and Torkelson, T. (2019) Strategies in Mitigating Stress Corrosion Cracking of Zircaloy-4 Fuel Sheathing: A Case for Polysiloxane Coating. 14 th Int ernational Conf erence on CANDU Fue l , Mississauga, 21-24 July 2019, p. 10.
Farahani, M., Ferrier, G.A., Chan, P.K. and Corcoran, E.C. (2013) Beyond CANLUB: An Improved Alternative Coating Development. 12 th Int ernational Conf erence on CANDU Fuel , Kingston, 15-18 September 2013, 1-14.
Hoppe, N. and Thomas, G.R. (1978) EPRI.
Heckman, H. and Strasser, A. (1978) American Nuclear Society Topical Meeting on Water Reactor Fuel Performance, 189-196.
Cox, B. (1990) Environmentally-induced Cracking of Zirconium Alloys—A Review. Journal of Nuclear Materials , 170, 1-23. https://doi.org/10.1016/0022-3115(90)90321-d
Quastel, A.D., Corcoran, E.C. and Lewis, B.J. (2013) The Effect of Oxidized UO2 on Iodine Induced Stress Corrosion Cracking of Fuel Sheathing. 12 th Int ernational Conf erence on CANDU Fuel , Kingston, 15-18 September 2013, 1-14.
Blake, A. (1990) Practical Stress Analysis in Engineering Design. 2nd Edition, Marcel Dikker, Inc., 292-294.
Rosinger, H.E. and Northwood, D.O. (1979) The Elastic Properties of Zirconium Alloy Fuel Cladding and Pressure Tubing Materials. Journal of Nuclear Materials , 79, 170-179. https://doi.org/10.1016/0022-3115(79)90444-6
Oding, I.A., Ivanova, V.S., Burdukskii, V.V. and Geminov, V.N. (1965) Creep and Stress Relaxation in Metals. Oliver and Boyd, 270-271.
Ferrier, G.A., Metzler, J., Farahani, M., Chan, P.K. and Corcoran, E.C. (2014) Dynamic Thermo-Chemo-Mechanical Strain of Zircaloy-4 Slotted Rings for Evaluating Strategies That Mitigate Stress Corrosion Cracking. The 19 th Pacific Basin Nuclear Conference , Vancouver, 24-28 August 2014. https://www.osti.gov/etdeweb/biblio/22670344
Waheed, A., Palleck, S., Chakraborthy, K. and Roth, M. (2008) Fatigue Tests on CANDU Fuel, Zircaloy Tubes for AECL Loading Following Program—Romania. 10 th CNS Int ernational Conf erence on CANDU Fuel , Ottawa, 5-8 October 2008. https://www.osti.gov/etdeweb/biblio/21296872
Lemoine, P., Darchis, L., Pelchat, J., Mardon, J.P. and Grosgeorge, M. (1988) Sustained Fatigue of Zircaloy-4 Claddings—Non-Irradiated Material. IAEA Technical Committee Meeting on Power Ramping , Cycling , and Load Following Behaviour of Water Reactor Fuel , Lyon, 45-54.
Jezequel, T., Auzoux, Q., Le Boulch, D., Bono, M., Andrieu, E., Blanc, C., et al. (2018) Stress Corrosion Crack Initiation of Zircaloy-4 Cladding Tubes in an Iodine Vapor Environment during Creep, Relaxation, and Constant Strain Rate Tests. Journal of Nuclear Materials , 499, 641-651. https://doi.org/10.1016/j.jnucmat.2017.07.014
Haddad, R. and Dorado, A. (1994) Grain-by-Grain Study of the Mechanisms of Crack Propagation during Iodine Stress Corrosion Cracking of Zircaloy-4. In: Garde, A.M. and Bradley, E.R., Eds., Zirconium in the Nuclear Industry : Tenth International Symposium , ASTM International, 559-575. https://doi.org/10.1520/stp15209s
Jacques, P., Lefebvre, F. and Lemaignan, C. (1999) Deformation-Corrosion Interactions for Zr Alloys during I-SCC Crack Initiation. Journal of Nuclear Materials , 264, 239-248. https://doi.org/10.1016/s0022-3115(98)00501-7
Farina, S.B., Duffo, G.S. and Galvele, J.R. (2002) Corrosion’2002, 57th Annual Conf. & Exposition, Denver, 7-12 April 2002, Paper No. 02436.
Jalilibal, Z., Amiri, A., Castagliola, P. and Khoo, M.B.C. (2021) Monitoring the Coefficient of Variation: A Literature Review. Computers & Industrial Engineering , 161, Article ID: 107600. https://doi.org/10.1016/j.cie.2021.107600
Ferrier, G.A., Farahani, M., Metzler, J., Chan, P.K. and Corcoran, E.C. (2016) J. Nucl. Eng. Radiat. Sci., 2, 21004, 2016.
Totten, G. (2005) Handbook on Residual Stress, Vol. 1. SEM.
Cox, B. and Haddad, R. (1987) Recent Studies of Crack Initiation during Stress Corrosion Cracking of Zirconium Alloys. In: Garde, A.M. and Bradley, E.R., Eds., Zirconium in the Nuclear Industry , ASTM International, 717-733. https://doi.org/10.1520/stp28155s
Cox, B. (1977) Transient Species Participating in the SCC of Zirconium Alloys. Corrosion , 33, 79-84. https://doi.org/10.5006/0010-9312-33.3.79