Delayed hydride cracking in irradiated Zircaloy cladding

ASTM Special Technical Publication

Volumn , Issue 1354, 2000, Pages 340-355

  Efsing, Pål ^a,b   Pettersson, Kjell ^a  

^a ROYAL INSTITUTE OF TECHNOLOGY   (Sweden)

^b Box 524   (Sweden)

Author keywords

[No Author keywords available]

Indexed keywords

CRACK INITIATION; CRACK PROPAGATION; DIFFUSION IN SOLIDS; FATIGUE OF MATERIALS; FRACTOGRAPHY; HYDROGEN EMBRITTLEMENT; NEUTRON IRRADIATION; NUCLEAR FUEL CLADDING; PRECIPITATION (CHEMICAL); RADIATION EFFECTS; STRESS CONCENTRATION; STRESS INTENSITY FACTORS;

DELAYED HYDRIDE CRACKING; ZIRCONIUM ALLOY ZIRCALOY;

ZIRCONIUM ALLOYS;

EID: 0033888346     PISSN: 10403094     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1520/stp14307s     Document Type: Conference Paper

References (12)

1. Armijo, J., "Performance of BWR Fuel," Proceedings of the 1994 International Topical Meeting on Light Water Reactor Fuel Performance in West Palm Beach - Florida, American Nuclear Society, 1995.
2. Lundholm, L., Efsing, P., Lysell, G., and Schrire, D., "Secondary Fuel Failure Crack Propagation Mechanisms," Proceedings of the Enlarged Halden Group Meeting at Storefjell, Norway, HRP-343, Vol. II, 1993.
3. Lin, K.-F., Chung, C.-S., Yeh, J.-J., Chen, J.-H., Chu, S.-S., and Lin, L. F., "Investigation on the Post-Defect Deterioration of Nonbarrier BWR Failed Rods," Proceedings of the 1994 International Topical Meeting on Light Water Reactor Fuel Performance in West Palm Beach - Florida, American Nuclear Society, 1994.
4. Efsing, P. and Pettersson, K., "The Influence of Temperature and Yield Strength on Delayed Hydride Cracking in Hydrided Zircaloy-2," Zirconium in the Nuclear Industry: Eleventh International Symposium, ASTM STP 1295, E. R. Bradley and G. P. Sabol, Eds., ASTM, 1996, pp. 394-404.
5. Mills, J. W. and Huang, F. H., Engineering Fracture Mechanics, Vol. 39, 1991, pp. 241-257.
6. Carpenter, G. J. C. and Watters, J. F., "Irradiation Damage Recovery in Some Zirconium Alloys," Zirconium in Nuclear Applications, ASTM STP 551, J. H. Schemel and H. S. Rosenbaum, Eds., ASTM, Philadelphia, 1974, pp. 400-415.
7. Pettersson, K., Vesterlund, G., and Andersson, T., "Effect of Irradiation on the Strength, Ductility and Defect Sensitivity of Fully Recrystallized Zircaloy Tube," Zirconium in the Nuclear Industry: Fourth International Symposium, ASTM STP 681, ASTM, Philadelphia, 1979, pp. 155-173.
8. Shi, S.-Q. and Puls, M. P., Journal of Nuclear Materials, Vol. 218, 1994, pp. 30-36.
9. Shi, S.-Q. and Puls, M. P., Journal of Nuclear Materials, Vol. 208, 1994, pp. 232-242.
10. Kese, K., SKI Rapport 98:30, Swedish Nuclear Power Inspectorate, 1998.
11. Lysell, G. and Grigoriev, V., IAEA Technical Committee Meeting on "High Burnup Fuel Specially Oriented to Fuel Chemistry and Pellet-Clad Interaction," Nyköping, Sweden, 7-10 Sept. 1998.
12. Sagat, S., Coleman, C. E., Griffiths, M., and Wilkins, B. J. S., "The Effects of Fluence and Irradiation Temperature on Delayed Hydride Cracking in Zr-2.5Nb," Zirconium in the Nuclear Industry: Tenth International Symposium, ASTM STP 1245, American Society of Testing and Materials, West Conshohocken, PA, 1993, pp. 35-61.