The PROMETRA program: Fuel cladding mechanical behavior under high strain rate

Nuclear Technology

Volumn 157, Issue 3, 2007, Pages 215-229

  Cazalis, Bernard ^a   Desquines, J ^a   Poussard, C ^b   Petit, M ^a   Monerie, Y ^a   Bernaudat, C ^c   Yvon, P ^b   Averty, X ^b  

^a INSTITUT DE RADIOPROTECTION ET DE SÛRETÉ NUCLÉAIRE IRSN   (France)

^b DIF   (France)

^c EDF R AND D   (France)

Author keywords

Irradiated fuel cladding; Mechanical properties; PROMETRA

Indexed keywords

BRITTLENESS; NUCLEAR REACTOR ACCIDENTS; REACTIVITY (NUCLEAR); STRAIN RATE; STRESS RELIEF; TENSILE PROPERTIES;

IRRADIATED FUEL CLADDING; REACTIVITY-INITIATED ACCIDENT LOADING;

NUCLEAR FUEL CLADDING;

EID: 33947528600     PISSN: 00295450     EISSN: None     Source Type: Journal    
DOI: 10.13182/NT07-A3814     Document Type: Article

References (20)

1. J. PAPIN, B. CAZALIS, J. M. FRIZONNET, J. DESQUINES, F. LEMOINE, V. GEORGENTHUM, F. LAMARE, and M. PETIT, "Summary and Interpretation of the CABRI REP-Na Program," Nucl. Technol., 157, 230 (2007).
2. J. PAPIN, C. LECOMTE, and J. C. MELIS, "Definition and Status of the CABRI International Program for High Burnup Fuel Studies," Proc. 28th WRSM, Bethesda, Maryland, October 23-25, 2000 (2000).
3. M. BALOURDET, C. BERNAUDAT, V. BASINI, and N. HOURDEQUIN, "The PROMETRA Programme: Assessment of Mechanical Properties of Zercaloy 4 Fuel Properties During an RIA," Trans. 15th Int. Conf. Structural Mechanics in Reactor Technology (SMiRT-15), Seoul, Korea, August 15-20, 1999, p. II-485 (1999).
4. P. YVON, C. SAINTE CATHERINE, C. DUGUAY, S. CARASSOU, N. HOURDEQUIN, B. CAZALIS, and C. BERNAUDAT, "Development of New Techniques to Assess the Mechanical Behaviour of Zircaloy-4 During an RIA," presented at IAEA Technical Committee Mtg. Fuel Behavior Under Transient LOCA Conditions, Halden, Norway, September 10-14, 2001.
5. B. CAZALIS, J. DESQUINES, C. BERNAUDAT, C. POUSSARD, X. AVERTY, and P. YVON, "The PROMETRA Program: A Reliable Material Database for Highly Irradiated Zircaloy-4, Zirlo, M5 Fuel Claddings," Proc. SMIRT-18, Beijing, China, August 7-12, 2005 (2005)
6. J. DESQUINES, B. CAZALIS, C. BERNAUDAT, C. POUSSARD, X. AVERTY, and P. YVON, "Zircaloy-4 Feel Cladding Mechanical Behavior in the Field of RIA Transients Through the PROMETRA Program," Proc. Conf. Zirconium in the Nuclear Industry, Stockholm, Sweden, June 2004, American Society for Testing and Materials (2004).
7. E. FEDERICI, F. LAMARE, V. BESSIRON, and J. PAPIN, "Status of Development of the SCANAIR Code for the Description of Fuel Behavior Under Reactivity Initiated Accidents," presented at Int. Topl. Mtg. Light Water Reactor Fuel Performance, Park City, Utah, April 10-13, 2000.
8. E. FEDERICI, F. LAMARE, V. BESSIRON, and J. PAPIN, "The SCANAIR Code Version 3.2: Main Features and Status of Qualifications," presented at IAEA Technical Committee Mtg. Fuel Behavior Under Transient LOCA Coditions, Halden, Norway, September 10-14, 2001.
9. CAST3M, CEA Saclay Finite Element Code, available on the Internet at http://www-cast3m.cea.fr/cast3m
10. X. AVERTY, P. YVON, C. DUGUAY, J. P. PIZZANELLI, and V. BASINI, "Induction Heating on Dynamic Tensile Tests in CEA Saclay," Proc. 39th Mtg. European Hotlabs at CIEMAT, Madrid, Spain, October 22-24, 2001, p. 39 (2001).
11. T. M. LINK, D. A. KOSS, and A. T. MOTTA, "Failure of Zircaloy Cladding Under Transverse Plane-Strain Deformation," Nucl. Eng. Des., 186, 379 (1998).
12. F. YUNCHANG and D.A. KOSS, "The Influence of Multi-axial States of Stress on the Hydrogen Embrittlement of Zirconium Alloy Sheet," Metal. Trans. A, 16, 675 (1985).
13. A. GLENDENING, D. A. KOSS, A. T. MOTTA, O. N. PIERRON, and R. S. DAUM, "The Influence of Strian State on the Failure of Hydrided Zimaloy-4," Proc. Conf. Zirconium in the Nuclear Industry, Stockholm, Sweden, June 2004, American Society for Testing and Materials (2004).
14. A. M. GARDE, G. P. SMITH, and R. C. PIREK, "Effects of Hydride Precipitate Localization and Neutron Fluence on the Ductility of Irradiated Zircaloy-4," Proc. 11th Int. Symp. Zirconium in the Nuclear Industry, ASTM STP 1295, p. 407, E. R. BRADLEY and G. P. SABOL, Eds., American Society for Testing and Materials (1996).
15. G. DOMMIZZI, R. A. ENRIQUE, J. OVEJERO-GARCIA, and G. C. BUSCAGLIA, "Blister Growth in Zirconium Alloys: Experimentation and Modeling," J. Nucl. Mater., 229, 36 (1996).
16. M. BLAT and D. NOEL, "Detrimental Role of Hydrogen on the Corrosion Rate of Zirconium Alloys," Proc. 11th Int. Symp. Zirconium in the Nuclear Industry, ASTM STP 1295, p. 319, E. R. BRADLEY and G. P. SABOL, Eds., American Society for Testing and Materials (1996).
17. O. N. PIERRON, D. A. KOSS, A. T. MOTTA, and K. S. CHAN, "The Influence of Hydride Blisters on the Fracture of Zircaloy-4," J. Nucl. Mater., 322, 21 (2003).
18. R. S. DAUM, S. MAJUMDAR, D. W. BATES, A. T. MOTTA, D. A. KOSS, and M. C. BILLONE, "On the Embritlement of Zircaloy-4 Under RIA-Relevant Conditions," Proc. 13th Int. Symp. Zirconium in the Nuclear Industry, ASTM STP 1423, p. 702, G. D. MOAN and P. RUDLING, Eds., West Conshohocken, Pennsylvania, 2002, American Society for Testing and Materials (2002).
19. D. W. BATES, "Influence of Stress States and Hydrogen on Deformation and Failure of Zircaloy-4," Thesis, Nucleus Engineering, The Pennsylvania State University (1998).
20. F. YUNCHANG and D.A. KOSS, "The Influence of Multi-axial State of Stress on the Hydrogen Embrittlement of Zirconium Alloy Sheet," Metal. Trans. A, 16, 675 (1985).