Characteristics of hydride precipitation and reorientation in spent-fuel cladding

ASTM Special Technical Publication

Volumn , Issue 1423, 2002, Pages 561-580

  Chung, H M ^a   Daum, R S ^a   Hiller, J M ^a   Billone, M C ^a  

^a ARGONNE NATIONAL LABORATORY   (United States)

Author keywords

Habit plane, texture; Macroscopic and microscopic hydrides; Radial and tangential hydrides; Spent fuel cladding; c type dislocations

Indexed keywords

CRYSTALLOGRAPHY; DISLOCATIONS (CRYSTALS); HYDRIDES; MICROSTRUCTURE; OPTICAL MICROSCOPY; PRECIPITATION (CHEMICAL); SPENT FUELS; STRESSES; TRANSMISSION ELECTRON MICROSCOPY; ZIRCONIUM ALLOYS;

HABIT PLANES; MACROSCOPIC HYDRIDES; MICROSCOPIC HYDRIDES; RADIAL HYDRIDES; SPENT-FUEL CLADDING; TANGENTIAL HYDRIDES;

NUCLEAR FUEL CLADDING;

EID: 8844271722     PISSN: 00660558     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1520/stp11406s     Document Type: Conference Paper

References (28)

1. Efsing, P. and Petterson, K., "The Influence of Temperature and Yield Strength on Delayed Hydride Cracking in Hydrided Zircaloy-2," Zirconium in the Nuclear Industry, 11th International Symposium, ASTM STP 1295, 1996, p. 394.
2. Grigoriev, V. and Josefsson, B., "On the Mechanism of Zircaloy Cladding Axial Splits," Journal of Nuclear Materials, Vol. 257, 1998, p. 99.
3. Lysell, G. and Grigoriev, V., "Characteristics of Axial Splits in Failed BWR Fuel Rods," Proceedings, 9th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, The Minerals, Metals, and Materials Society, Warrendale, PA, 1999, pp. 1169-1175.
4. Edsinger, K., Vaidyanathan, S., and Adamson, R. B., "On the Mechanism of Axial Splits in Failed BWR Fuel Rods," Proceedings, 9th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, The Minerals, Metals, and Materials Society, Warrendale, PA, 1999, pp. 1191-1199.
5. Petterson, K., Kese, K., and Efsing, P., "Studies on Delayed Hydride Cracking of Zircaloy Cladding," Proceedings, 9th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, The Minerals, Metals, and Materials Society, Warrendale, PA, 1999, pp. 1201-1209.
6. Simpson, L. A. and Puls, M. P., "The Effects of Stress, Temperature, and Hydrogen Content on Hydride-Induced Crack Growth in Zr-2.5%Nb," Metallurgical Transactions A, 1979, p. 1093.
7. Puls, M. P., Simpson, L. A., and Dutton, R., "Hydride-Induced Crack Growth in Zirconium Alloys," Fracture Problems and Solutions in the Energy Industry, Pergamon Press, New York, 1982, p. 13.
8. Coleman, C. E., "Effect of Texture on Hydride Reorientation and Delayed Hydrogen Cracking in Cold-Worked Zr-2.5Nb," Zirconium in the Nuclear Industry, 5th International Symposium, ASTM STP 754, 1982, p. 393.
9. Chow, C. K. and Simpson, L. A., "Analysis of the Unstable Fracture of a Reactor Pressure Tube Using Fracture Toughness Mapping," Case Histories Involving Fatigue and Fracture Mechanics, ASTM STP 918, 1986, p. 78.
10. Cheadle, B. A., Coleman, C. E., and Ambler, J. F. R., "Prevention of Delayed Hydride Cracking in Zirconium Alloys," Zirconium in the Nuclear Industry, 7th International Symposium, ASTM STP 939, 1987, p. 224.
11. Coleman, C. E., Cheadle, B. A., Causey, A. R., Chow, C. K., Davies, P. H., McManus, M. D., Rodgers, D., Sagat, S., and van Drunen, G., "Evaluation of Zircaloy-2 Pressure Tubes from NPD," Zirconium in the Nuclear Industry, 8th International Symposium, ASTM STP 1023, 1989, p. 35.
12. Moan, G. D., Coleman, C. E., Price, E. G., Rodgers, D. K., and Sagat, S., "Leak-Before-Break in Pressure Tubes of CANDU Reactors," International Journal of Pressure Vessel & Piping, Vol. 43, 1990, p. 1.
13. Meyer, R. O., McCardell, R. K., Chung, H. M., Diamond, D. J., and Scott, H. H., "A Regulatory Assessment of Test Data for Reactivity-Initiated Accidents," Nuclear Safety, Vol. 37, 1996, p. 271.
14. Papin, J., Balourdet, M., Lemoine, F., Lamare, F., Frizonnet, J. M., and Schmitz, F., "French Studies on High-Burnup Fuel Transient Behavior under RIA Conditions," Nuclear Safety, Vol. 37, 1996, p. 289.
15. Chung, H. M. and Kassner, T. F., "Cladding Metallurgy and Fracture Behavior during Reactivity-Initiated Accidents at High Burnup," Journal of Nuclear Engineering and Design, Vol. 186, 1998, p. 411.
16. Fuketa, T., Nakamura, T., Sasajima, H., Nagase, H., and Uetsuka, H., "Behavior of PWR and BWR Fuels during Reactivity-Initiated Accident Conditions," Proceedings International Topical Mtg. on Light Water Reactor Fuel Performance, Park City, UT, American Nuclear Society, La Grange Park, IL, 2000, pp. 1133-1147.
17. Chung, H. M., "Fundamental Metallurgical Aspects of Axial Splitting in Zircaloy Cladding," Proceedings, International Topical Mtg. on Light Water Reactor Fuel Performance, Park City, UT, American Nuclear Society, La Grange Park, IL, 2000, pp. 1181-1200.
18. Einziger, R. E. and Kohli, R., "Low-Temperature Rupture Behavior of Zircaloy-Clad Pressurized Water Reactor Spent Fuel Rods Under Dry Storage Conditions," Nuclear Technology, Vol. 67, 1984, p. 107.
19. Goll, W. H., Spilker, H., and Toscano, E. H., "Short-Time Creep and Rupture Tests on High Burnup Fuel Rod Cladding," Journal of Nuclear Materials, Vol. 289, 2001, p. 247.
20. Garde, A. M., "Effects of Irradiation and Hydriding on the Mechanical Properties of Zircaloy-4 at High Fluence," Zirconium in the Nuclear Industry, 8th International Symposium, ASTM STP 1023, 1989, p. 548.
21. Garde, A. M., Smith, G. P., and Pirek, R. C., "Effects of Hydride Precipitate Localization and Neutron Fluence on the Ductility of Irradiated Zircaloy-4," Zirconium in the Nuclear Industry, 11th International Symposium, ASTM STP 1295, 1996, p. 407.
22. McMinn, A., Darby, E. C., and Schofield, J. S., "The Terminal Solubility of Hydrogen in Zirconium Alloys," Zirconium in the Nuclear Industry: 12th International Symposium, ASTM STP 1354, 2000, pp. 173-195.
23. Langeren, J. P. and Lehr, P. in Compt. Rend., Vol. 243, 1956, p. 151.
24. Langeren, J. P. and Lehr, P. in Review of Metallurgy, Vol. 60, 1958, p. 901.
25. Westlake, D. G. and Fischer, E. S. in Transactions of TMS-AIME, Vol. 224, 1962, p. 254.
26. Westlake, D. G., "The Habit Planes of Zirconium Hydride in Zirconium and Zircaloy," Journal of Nuclear Materials, Vol. 26, 1968, p. 208.
27. Chung, H. M., Yaggee, F. L., and Kassner, T. F., "Fracture Behavior and Microstructural Characteristics of Irradiated Zircaloy Cladding," Zirconium in the Nuclear Industry: 7th International Symposium, ASTM STP 939, 1987, pp. 775-801.
28. Chung, H. M., "Phase Transformations in Neutron-Irradiated Zircaloys," Radiation-Induced Changes in Microstructure, 13th International Symposium, ASTM STP 955, 1987, p. 676.