Impact of irradiation defects annealing on long-term thermal creep of irradiated zircaloy-4 cladding tube

ASTM Special Technical Publication

Volumn , Issue 1423, 2002, Pages 720-737

  Cappelaere, C ^a   Limon, R ^a   Gilbon, D ^a   Bredel, T ^a   Rabouille, O ^a   Bouffioux, P ^b   Mardon, J P ^c  

^a CEA SACLAY   (France)

^b EDF R AND D   (France)

^c AREVA NP   (France)

Author keywords

Cladding; Creep; Hydrides; Interim storage; Irradiation defects annealing; Rupture; Zircaloy

Indexed keywords

ANNEALING; CLADDING (COATING); CREEP TESTING; HELIUM; HYDRIDES; IRRADIATION; OPTICAL MICROSCOPY; PRESSURE EFFECTS; TRANSMISSION ELECTRON MICROSCOPY;

INTERIM STORAGE; IRRADIATION DEFECTS; IRRADIATION DEFECTS ANNEALING; THERMAL CREEP; ZIRCALOY;

ZIRCONIUM ALLOYS;

EID: 8844269147     PISSN: 00660558     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (10)

1. Limon, R., Cappelaere, C., Bredel, T., and Bouffioux, P., "A Formulation of the Spent Fuel Cladding Behaviour for Long Term Storage," ANS International Topic Meeting on Light Water Reactor Fuel Performance, Park City, UT, 10-13 April 2000.
2. Soniak, A., L'Hullier, N., Mardon, J. P., Rebeyrolles, V., Bouffioux, P., and Bernaudat, C., "Irradiation Creep Behavior of Zr-base Alloys," Zirconium in the Nuclear Industry: Thirteenth International Symposium, Annecy, France, 11-14 June 2001.
3. Robert-Bérat, L., "Influence d'une couche de zircone sur le comportement mécanique des tubes en Zircaloy-4," PHD, Université Biaise Pascal, Ecole Doctorale des Sciences Fondamentales, n° 1281, 2001, France.
4. Bérat-Robert, L., Pelchat, J., Limon, R., Maury, R., Pelé, J., Cappelaere, C., Prioul, C., Bouffioux, P., and Diz, J., "Influence of a Zirconia Layer on the Mechanical Behavior of Zircaloy-4 Cladding and Thimble Tubes," ANS International Topic Meeting on Light Water Reactor Fuel Performance, Park City, UT, 10-13 April 2000.
5. Bouffioux, P. and Legras, L., "Effect of Hydriding on the Residual Cold Work Recovery and Creep of Zircaloy-4 Cladding Tubes," ANS International Topic Meeting on Light Water Reactor Fuel Performance, Park City, UT, 10-13 April 2000.
6. Gilbon, D. and Simonot, C., "Effect of Irradiation on the Microstructure of Zircaloy-4," Zirconium in the Nuclear Industry: Tenth International Symposium, ASTM STP 1245, Philadelphia, 1994.
7. Chan, K. S., "A Micromechanical Model for Predicting Hydride Embrittlement in Nuclear Fuel Cladding Material," Journal of Nuclear Materials, Vol. 227, 1996.
8. Bai, J. B., Ji, N., Gilbon, D., Prioul, C., and François, D., "Hydride Embrittlement in Zircaloy-4 Plate: Part II. Interaction Between the Tensile Stress and the Hydride Morphology," Metallurgical and Materials Transactions A, Volume 25A, June 1994.
9. Einziger, R. and Kohli, R., "Low Temperature Rupture Behavior of Zircaloy-Clad Pressurized Water Reactor Spent Fuel Rods Under Dry Storage Conditions," Nuclear Technology, No. 67, 1984, pp. 107-123.
10. Efsing, P. and Pettersson, K., "Delayed Hydride Cracking in Irradiated Zircaloy. Cladding," Zirconium in the Nuclear Industry: Twelfth International Symposium, ASTM STP 1354, West Conshohocken, PA, 2000, pp. 340-355.