Effects of thermomechanical processing on in-reactor corrosion and post-irradiation mechanical properties of zircaloy-2

ASTM Special Technical Publication

Volumn 1295, Issue , 1996, Pages 726-757

  Huang, Peter Y ^a   Mahmood, S Tahir ^a   Adamson, Ronald B ^a  

^a GE ENERGY   (United States)

Author keywords

BWR; Corrosion resistance; Intermetallic precipitates; Irradiation; Irradiation hardening; Precipitate dissolution; Tensile properties; Thermomechanical processing; Zircaloy 2

Indexed keywords

BOILING WATER REACTORS; CORROSION RESISTANCE; METALLOGRAPHIC MICROSTRUCTURE; NEUTRON IRRADIATION; PARTICLE SIZE ANALYSIS; PRECIPITATION (CHEMICAL); RADIATION EFFECTS; SPECIMEN PREPARATION;

MICROSTRUCTURE EVOLUTION; ZIRCONIUM ALLOY ZIRCALOY 2;

ZIRCONIUM ALLOYS;

EID: 0030291865     PISSN: 00660558     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1520/stp16199s     Document Type: Article

References (38)

1. Marlowe, M. O., Armijo, J. S., Cheng, B., and Adamson, R. B., "Nuclear Fuel Cladding Localized Corrosion," Light Water Reactor Fuel Performance, Proceedings of American Nuclear Society Topical Meeting, Orlando, FL, 1985, ANS, La Grange Park, IL, pp. 3-73.
2. Rudling, P., Vannesjo, K. L., Vesterlund, G., and Massih, A. R., "Influence of Second-Phase Particles on Zircaloy Corrosion in BWR Environment," Zirconium in the Nuclear Industry: Seventh International Symposium, ASTM STP 939, R. B. Adamson and L. F. P. Van Swarn, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1987, pp. 292-306.
3. Maussner, G., Steinberg, E., and Tenckhoff, E., "Nucleation and Growth of Intermetallic Precipitates in Zircaloy-2 and Zircaloy-4 and Correlation to Nodular Corrosion Behavior," Zirconium in the Nuclear Industry: Seventh International Symposium, ASTM STP 939, American Society for Testing and Materials, West Conshohocken, PA, 1987, pp. 307-320.
4. Andersson, T. and Thorvaldsson, T., "Nodular Corrosion Resistance of Zircaloy-2 in Relation to Second-Phase Particle Distribution," Zirconium in the Nuclear Industry: Seventh International Symposium, ASTM STP 939, R. B. Adamson and L. F. P. Van Swan, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1987, pp. 321-337.
5. Bangaru, N. V., Busch, R. A., and Schemel, J. H., "Effect of Beta Quenching on the Microstructure and Corrosion of Zircaloys," Zirconium in the Nuclear Industry: Seventh International Symposium, ASTM STP 939, R. B. Adamson and L. F. P. Van Swam, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1987, pp. 341-363.
6. Cheng, B. and Adamson, R. B., "Mechanistic Studies of Zircaloy Nodular Corrosion," Zirconium in the Nuclear Industry: Seventh International Symposium, ASTM STP 939, American Society for Testing and Materials, West Conshohocken, PA, 1987, pp. 387-416.
7. Garzarolli, F., Stehle, H., Steinberg, E., and Weidinger, H., "Progress in the Knowledge of Nocular Corrosion," Zirconium in the Nuclear Industry: Seventh International Symposium, ASTM STP 939, R. B. Adamson and L. F. P. Van Swam, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1987, pp. 417-430.
8. Cheng, B., Adamson, R. B., Bell, W. L., and Proebstle, R. A., "Corrosion Performance of Some Zirconium Alloys Irradiated in the Steam Generating Heavy Water Reactor Winfrith," Proceedings of International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Myrtle Beach, SC, 22-25 Aug. 1983, TMS, Warrendale, PA, pp. 274-285.
9. Yang, W. J. S. in Journal of Nuclear Materials, Vol. 158, 1988, p. 71.
10. Yang, W. J. S. and Adamson, R. B., "Beta-Quenched Zircaloy-4: Effects of Thermal Aging and Neutron Irradiation," Zirconium in the Nuclear Industry: Eighth International Symposium, ASTM STP 1023, L. F. P. Van Swam and C. M. Eucken, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1989, pp. 451-477.
11. Yang, W. J. S., Tucker, R. P., Cheng, B., and Adamson, R. B. in Journal of Nuclear Materials, 1986, Vol. 138, p. 185.
12. Kruger, R. M., "Precipitate Stability in Zircaloy-2," EPRI NP-6845-D, Electric Power Research Institute, Palo Alto, PA, 1990.
13. Kruger, R. M. and Adamson, R. B. in Journal of Nuclear Materials, Vol. 205, 1993, p. 242.
14. Griffiths, M., Gilbert, R. W., and Carpenter, G. J. C. in Journal of Nuclear Materials, Vol. 150, 1987, p. 53.
15. Gilbert, R. W., Giffiths, M., and Carpenter, G. J. C. in Journal of Nuclear Materials, Vol. 135, 1985, p. 265.
16. Etoh, Y., Kikuchi, K., Yasuda, T., Koizumi, S., and Oishi, M. in Proceedings, International Topical Meeting on LWR Fuel Performance, Avignon, 1991, American Nuclear Society, La Grange Park, IL, p. 691.
17. Etoh, Y., Shimada, S., Kikuchi, K., and Kawai, K. in Journal of Nuclear Science and Technology, Vol. 29, 1992, pp. 1173-1183.
18. Cheng, B.-C., Kruger, R. M., and Adamson, R. B., "Corrosion Behavior of Irradiated Zircaloy," Zirconium in the Nuclear Industry: Tenth International Symposium, ASTM STP 1245, A. M. Garde and E. R. Bradley, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1994, pp. 400-418.
19. Kruger, R. M., Adamson, R. B., and Brenner, S. S. in Journal of Nuclear Materials, Vol. 189, 1992, p. 193.
20. Garzarolli, F., Schumann, R., and Steinberg, E., "Corrosion Optimized Zircaloy for Boiling Water Reactor (BWR) Fuel Elements," Zirconium in the Nuclear Industry: Tenth International Symposium, ASTM STP 1245, A. M. Garde and E. R. Bradley, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1994, pp. 709-723.
21. 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 1023, L. F. P. Van Swam and C. M. Eucken, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1989, pp. 548-569.
22. Baumgartner, J. A., "BWR Fuel Bundle Extended Burnup Final Report," DOE/ET/34031-18, UC-78, U.S. Department of Energy, December 1984.
23. Reager, R. D., to be published.
24. Griffiths, M., Gilbert, R. W., and Carpenter, G. J. C. in Journal of Nuclear Materials, Vol. 150, 1987, p. 53.
25. Motta, A. T. and Lemaignan, C. in Journal of Nuclear Materials, Vol. 195, 1992, pp. 277-285.
26. Holt, R. A. and Gilbert, R. W., "〈c〉 Component Dislocations in Neutron Irradiated Zircaloy-2," Journal of Nuclear Materials, Vol. 116, 1983, p. 127.
27. Etoh, Y. and Shimada, S. in Journal of Nuclear Materials, Vol. 200, 1993, p. 59.
28. Fidleris, V., Tucker, R. P., and Adamson, R. B., "An Overview of Microstructural and Experimental Factors That Affect the Irradiation Growth Behavior of Zirconium Alloys," Zirconium in the Nuclear Industry, Seventh International Symposium, ASTM STP 939, R. B. Adamson and L. F. P. Van Swam, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1987, pp. 49-85.
29. Edsinger, K. W., Kruger, R. M., and Huang, P. Y., to be published.
30. Taylor, D. F., "An Oxide-semiconductance Model of Nodular Corrosion and Its Application to Zirconium Alloy Development," Journal of Nuclear Materials, Vol. 184, 1991, pp. 65-77.
31. Inagaki, M., Kanno, M., and Maki, H., "Effect of Alloying Elements in Zircaloy on Photo-Electrochemical Characteristics of Zirconium Oxide Films," Zirconium in the Nuclear Industry: Ninth International Symposium, ASTM STP 1132, C. M. Eucken and A. M. Garde, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1991, pp. 437-460.
32. Harding, J. H., "The Effect of Alloying Elements on Zircaloy Corrosion," Journal of Nuclear Materials, Vol. 202, 1993, pp. 216-221.
33. Van Swam, L. F. P. and Shann, S. H., "The Corrosion of Zircaloy-4 Fuel Cladding in Pressurized Water Reactors," Zirconium in the Nuclear Industry: Ninth International Symposium, ASTM STP 1132, C. M. Eucken and A. M. Garde, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1991, pp. 758-781.
34. Hutchinson, B. and Lehtinen, B., "A Theory of the Resistance of Zircaloy to Uniform Corrosion," Journal of Nuclear Materials, Vol. 217, 1994, pp. 243-249.
35. Cheng, B., Adamson, R. B., Machiels, A. J., and O'Boyle, D., "Effect of Hydrogen Water Chemistry on Fuel Performance at Dresden-2," International Topical Meeting on LWR Fuel Performance, Proceedings of the American Nuclear Society Topical Meeting, Avignon, France, 1991, American Nuclear Society, La Grange Park, IL, p. 664.
36. Charquet, D., Rudling, P., Mikes-Lindback, M., and Barberis, P., "Hydrogen Absorption Kinetics During Zircaloy Oxidation in Steam," Zirconium in the Nuclear Industry: Tenth International Symposium, ASTM STP 1245, A. M. Garde and E. R. Bradley, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1994, pp. 80-97.
37. Levin, H. A. and Garcia, S. E., "BWR Fuel Experience with Zinc Injection," NACE 7th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Breckenridge, CO, 6-10 Aug. 1995, Paper 63, TMS, Warrendale, PA.
38. Adamson, R. B. and Bell, W. L., "Effects of Neutron Irradiation and Oxygen Content on the Microstructure and Mechanical Properties of Zircaloy," Microstructure and Mechanical Behaviour of Materials, X'ian, China, Vol. 1, 21-24 Oct. 1985, Engineering Materials Advisory Services, Ltd Warley, UK.