Long term behavior of the spent fuel cladding in dry storage conditions

Proceedings of the International Conference on Radioactive Waste Management and Environmental Remediation, ICEM

Volumn 1, Issue , 2001, Pages 195-200

  Cappelaere, C ^a   Limon, R ^a   Bredel, T ^a   Herter, P ^a   Gilbon, D ^a   Bouffioux, Pol ^b   Mardon, Jean Paul ^c  

^a JANNUS Saclay Laboratory   (France)

^b R and D Division   (France)

^c AREVA NP   (France)

Author keywords

[No Author keywords available]

Indexed keywords

ANNEALING; COMPUTER SIMULATION; CREEP TESTING; EQUATIONS OF STATE; FUEL STORAGE; IRRADIATION; NUCLEAR FUEL CLADDING; OPTICAL MICROSCOPY; OXIDATION; PRESSURE EFFECTS; RADIOACTIVE WASTE DISPOSAL; RADIOACTIVE WASTE STORAGE;

THERMAL CREEPS; VACUUM DRYING;

SPENT FUELS;

EID: 0346331502     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (7)

1. P BOUFFIOUX, S LECLERCQ, C CAPPELAERE, T BREDEL: «Interim Dry Storage of PWR Spent Fuel Assemblies - Development of a Long Term Creep Law to Assess the Fuel Cladding Integrity" - ICEM 2001 - 8th International Conference on Radioactive Waste Management and Environmental Remediation - Bruges, October 2001
2. R. LIMON, C CAPPELAERE, T BREDEL, P BOUFFIOUX: "A formulation of the spent fuel cladding behavior for long term storage" - ANS International Topic Meeting on Light water Reactor Fuel Performance, Park City, Utah, April 10-13, 2000
3. th International Symposium, Annecy, France, June 11-14, 2001
4. L BERAT - PHD - 2001 - To be published.
5. L BERAT-ROBERT, J PELCHAT, R LIMON, R MAURY, J PELE, C CAPPELAERE, C PRIOUL, P BOUFFIOUX, J DIZ: « 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, Utah, April 10-13, 2000
6. P. BOUFFIOUX, L. LEGRAS « 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, Utah, April 10-13, 2000
7. B. F. KAMMENZIND, D. G. FRANKLIN, H. R. PETERS AND W. J. DUFFIN, "Hydrogen Pick-up and Redistribution in Alpha-Annealed Zircaloy-4", Zirconium in the Nuclear Industry, ASTM-STP 1295, Eds. E. R. Bradley and G. P. Sabol, American Society for Testing and Materials, 1996, P. 338.