Failure mechanisms of irradiated Zr alloys related to PCI: Activated slip systems, localized strains, and iodine-induced stress corrosion cracking

ASTM Special Technical Publication

Volumn , Issue 1354, 2000, Pages 377-398

  Fregonese, M ^a   Regnard C ^a   Rouillon, L ^a   Magnin, T ^b   Lefebvre, F ^a   Lemaignan, C ^a  

^a CEA GRENOBLE   (France)

^b ECOLE DES MINES DE SAINT ETIENNE   (France)

Author keywords

[No Author keywords available]

Indexed keywords

ADSORPTION; CRACK INITIATION; FAILURE (MECHANICAL); IODINE; METHANOL; NEUTRON IRRADIATION; NUCLEAR FUEL CLADDING; RADIATION DAMAGE; RADIATION HARDENING; SHEAR DEFORMATION; STRAIN; STRESS CORROSION CRACKING;

STRAIN SOFTENING; ZIRCONIUM ALLOY ZIRCALOY-4;

ZIRCONIUM ALLOYS;

EID: 0343526869     PISSN: 10403094     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1520/stp14309s     Document Type: Conference Paper

References (37)

1. Cox, B. and Wood, J. C., "Iodine Induced Cracking of Zircaloy Fuel Cladding, a Review," reprinted from Corrosion Problems in Energy Conversion and Generation, 1974, AECL Report 4936.
2. Cox, B., "Pellet Clad Interaction (PCI) Failures of Zirconium Fuel Cladding, a Review," Journal of Nuclear Materials, Vol. 172, 1990, pp. 249-292.
3. Cubiccioti, D. and Jones, R. L., "EPRI-NASA Cooperative Project on Stress Corrosion Cracking of Zircaloys," EPRI Research Project 455-1, EPRI NP-717, 1978.
4. Cubicciotti, D., Jones, R. L., and Syrett, B. C., "Chemical Aspects of Iodine Induced Stress Corrosion Cracking of Zircaloys," Zirconium in the Nuclear Industry (5th Symposium), ASTM STP 754, 1982, pp. 146-157.
5. Götzmann, O., "Thermochemical Evaluation of PCI Failures in LWR Fuel Pins," Journal of Nuclear Materials, Vol. 107, 1982, pp. 185-195.
6. Konashi, K., "Estimation of Irradiation Induced Iodine Pressure in an LWR Fuel Rod," Journal of Nuclear Materials, Vol. 125, 1984, pp. 244-247.
7. Cox, B. and Wood, J. C., "The Mechanism of SCC of Zirconium Alloys in Halogens," Proceedings of the Conference of Mechanisms of Environment Sensitive Cracking of Materials, Guilford, UK, Metals Society of London, 1997, p. 520.
8. Gittus, J. H., "Theoretical Analysis of the Strains Produced in Nuclear Fuel Cladding Tubes by the Expansion of Cracked Cylindrical Fuel Pellets," Nuclear Engineering and Design, Vol. 18, 1972, pp. 69-82.
9. Caillot, L., Lemaignan, C., and Joseph, J. "In-Situ Measurements of Cladding Strain During Power Transients Using the DECOR Device," Proceedings of the ANS International Topical Meeting on Light Water Reactor Fuel Performance, West Palm Beach, FL, April 1994.
10. Grounes, M., "Studsvik's Fuel R&D Projects," proceeding of a IAEA technical committee meeting, Windermere, UK, September 1994, IAEA-TECDOC-957.
11. Haddad, R. E. and Cox, B., "On the Initiation of Cracks in Zircaloy Tubes by 12 and Cs/Cd Vapours," Journal of Nuclear Materials, Vol. 138, 1986, pp. 81-88.
12. Hofman, P., "Corrosion Induced Failure of Internally Pressurized Zircaloy Tubes at High Temperatures," Proceedings of the European Symposium on Corrosion and Mechanical Stress at High Temperatures, Petten (NH), The Netherlands, 1980, pp. 135-149.
13. Hofman, P. and Spino, J., "Stress Corrosion Cracking of Zircaloy-4 Cladding at Elevated Temperatures and Its Relevance to Transcient LWR Fuel Rod Behavior," Journal of Nuclear Materials, Vol. 125, 1984, pp. 85-95.
14. Videm, K. and Lunde, L., "Stress Corrosion Cracking of Zircaloy Fuel Cladding Under Power Ramps and Laboratory Tests," ANS Topical Meeting Water Reactor Fuel Performance, St. Charles, 1977.
15. Une, K., "Stress Corrosion Cracking of Zircaloy-2 Cladding in Iodine Vapor," Journal of Nuclear Science and Technology, Vol. 14, No. 6, 1977, pp. 443-451.
16. Jacques, P., "Contribution à l'étude de l'amorçage des fissures de Corrosion Sous Contrainte par l'iode dans le Zircaloy-4," Thèse de Doctorat, I.N.P. Grenoble (France), 1994.
17. Schuster, I., Lemaignan, C., and Joseph, J., "Testing and Modeling the Influence of Irradiation on Iodine Induced Stress Corrosion Cracking of Zircaloy-4," Nuclear Engineering and Design, Vol. 156, 1995, pp. 343-349.
18. Magnin, T., "Advances in Corrosion-Deformation Interactions," Materials Science Forum, Vol. 202, 1996, Trans Tech Publication.
19. Williford, R. E., "Chemically Assisted Crack Nucleation in Zircaloy," Journal of Nuclear Materials, Vol. 132, 1985, pp. 52-61.
20. Cubicciotti, D. and Scott, A. C., "Kinetics of Formation of Solid Iodides on Zirconium," Journal of the Less Common Metals, Vol. 77, 1981, pp. 241-250.
21. Schuster, I. and Lemaignan, C., "Influence of Texture on Iodine-Induced Stress Corrosion Cracking of Zircaloy-4 Cladding Tubes," Journal of Nuclear Materials, Vol. 189, 1992, pp. 157-166.
22. Une, K., "Deformation and Fracture Behavior of Zircaloy-2 Deformed at Constant Rate in Iodine Environment (I)," Journal of Nuclear Science and Technology, Vol. 16, No. 8, 1979, pp. 577-587.
23. Une, K., "Deformation and Fracture Behavior of Zircaloy-2 Deformed at Constant Rate in Iodine Environment (II)," Journal of Nuclear Science and Technology, Vol. 16, No. 9, 1979, pp. 660-670.
24. Lee, D. and Adamson, R. B., "Modeling of Localized Deformation in Neutron Irradiated Zircaloy-2," Zirconium in Nuclear Industry, ASTM STP 633, American Society for Testing and Materials, 1977, pp. 385-401.
25. Hwang, S. K. and Han, H. T., "Anisotropic Surface Energy Reduction of Zr by Chemisorption," Journal of Nuclear Materials, Vol. 161, 1989, pp. 175-181.
26. Billaux, M. R., Shann, S. H., and Van Swam, L. F., "Transient Fuel Rod Behaviour Prediction with RODEX-3/SIERRA," proceeding of a IAEA technical committee meeting, Windermere, UK, September 1994, IAEA-TECDOC-957.
27. Hourdequin, N., "Contribution à la modélisation du comportement mécanique des combustibles REP sous irradiation, avec en particulier, le traitement de l'interaction pastille gaine dans un crayon combustible," Mémoire de Thèse CEA-R-5709, 1995.
28. Bement, A. L., "Radiation Damage in Hexagonal Close-Packed Metals and Alloys," Journal of Radiation Effects, Metallurgical Society Conferences, W. F. Sheely, Ed., Vol. 37, 1966, p. 671.
29. Onchi, T., Kayano, H., and Higashiguchi, J., "The Inhomogeneous Deformation Behaviour of Neutron Irradiated Zircaloy-2," Journal of Nuclear Materials, Vol. 88, 1980, pp. 226-235.
30. Adamson, R. B. and Bell, W. L., "Microstructure and Mechanical Behavior of Materials," Vol. 1, Proceedings of the International Symposium at X'ian, Republic of China, October 1985, Engineering Materials Advisory Services LTD, Warley, UK, p. 237.
31. Howe, L. M. and Thomas, W. R., "The Effect of Neutron Irradiation on the Tensile Properties of Zircaloy-2," Journal of Nuclear Materials, Vol. 2, 1960, pp. 248-260.
32. Higgy, H. R. and Hammad, F. H., "Effect of Neutron Irradiation on the Tensile Properties of Zircaloy-2 and Zircaloy-4," Journal of Nuclear Materials, Vol. 44, 1972, pp. 215-227.
33. Garde, A. M., "Effects of Irradiation and Hydriding on the Mechanical Properties of Zircaloy-4 at High Fluence," Zirconium in the Nuclear Industry: Eighth International Symposium, ASTM STP 766, 1989, pp. 548-569.
34. Jostsons, A., Kelly, P. M., and Blake, R. G., "The Nature of Dislocation Loops in Neutron Irradiated Zirconium," Journal of Nuclear Materials, Vol. 66, 1977, pp. 236-256.
35. Northwood, D. O., Gilbert, R. W., Bahen, L. E., Kelly, P. M., Blake, R. G., Jostsons, A., Madden, P. D., Faulkner, D., Bell, W., and Adamson, R. B., "Characterization of Neutron Irradiation Damage in Zirconium Alloys - An International 'Round-Robin' Experiment," Journal of Nuclear Materials, Vol. 79, 1979, pp. 379-394.
36. Nakatsuka, M. and Nagai, M., "Reduction of Plastic Anisotropy of Zircaloy Cladding by Neutron Irradiation, 1. Yield Loci Obtained from Knoop Hardness," Journal of Nuclear Science and Technology, Vol. 24, 1987, pp. 832-838.
37. Makin, M. J., "The Mechanism of Slip Band Growth in Irradiated Crystals" The Philosophical Magazine, Vol. 21, 1970, pp. 815-818.