Influence of long service exposures on the thermal-mechanical behavior of Zy-4 and M5™ alloys in LOCA conditions

Journal of ASTM International

Volumn 2, Issue 2, 2005, Pages 191-214

  Portier, Laurence ^a   Bredel, Thierry ^b   Brachet, Jean Christophe ^a   Maillot, Valerie ^a   Mardon, Jean Paul ^c   Lesbros, Anne ^d  

^a SRMA   (France)

^b CEA SACLAY   (France)

^c AREVA NP   (France)

^d EDF R AND D   (France)

Author keywords

Creep; Embrittlement; High temperature oxidation; Hydrogen effect; Irradiation defects; LOCA; M5 ; Oxygen content in prior beta phase; Quench; Residual ductility; Zirconium alloy; Zy 4

Indexed keywords

CREEP; HIGH TEMPERATURE APPLICATIONS; IRRADIATION; OXIDATION; PRESSURIZED WATER REACTORS; ZIRCONIUM ALLOYS;

HIGH TEMPERATURE OXIDATION; HYDROGEN EFFECTS; IRRADIATION DEFECTS; M5™; OXYGEN CONTENT IN PRIOR-BETA PHASE; RESIDUAL DUCTILITY; ZY-4;

LOSS OF COOLANT ACCIDENTS;

EID: 30644468473     PISSN: None     EISSN: None     Source Type: Journal    
DOI: 10.1007/3-540-27449-9_20     Document Type: Article

References (18)

1. Erbacher, F. J. and Leistikow S., "Zircaloy Fuel Cladding Behavior in a Loss-Of-Coolant Accident: A Review," Zirconium in the Nuclear Industry: Seventh International Symposium, ASTM STP 939, R. B. Adamson and L. F. P. Van Swam, Eds., ASTM International, West Conshohocken, PA, 1987, pp. 451-488.
2. Forgeron, T., Brachet, J.-C., Barcelo F., Castaing, A., Hivroz, J., Mardon, J.-P., et al., "Experiment and Modeling of Advanced Fuel Rod Cladding Behavior under LOCA Conditions: α<=>β Phase Transformation Kinetics and EDGAR Methodology," Zirconium in the Nuclear Industry: Twelfth International Symposium, ASTM STP 1354, G. P. Sabol and G. D. Moan, Eds., ASTM International, West Conshohocken, PA, 2000, pp. 256-278.
3. Brachet, J. C., Pelchat, J., Hamon, D., Maury, R., Jacques, P., and Mardon J.-P., "Mechanical Behavior at Room Temperature and Metallurgical Study of Low-Tin Zy-4 and M5TM (Zr-NbO) Alloys after Oxidation at 1100°C and Quenching," Proceeding on Fuel behavior and LOCA conditions organized by IAEA, Sept. 10-14, 2001, IAEA-TECDOC-1320.
4. th International Symposium, June 10-14 2001, Annecy, France, ASTM STP 1423, G. D. Moan and P. Rudling, Eds., ASTM International, West Conshohocken, PA, 2002, pp. 673-701.
5. Hozer Z., Griger A., Matus L., Vasaros L., and Horvath M., "Effect of Hydrogen Content on the Embrittlement of Zr Alloys," Proceeding of TCM on "Fuel behavior under transient and LOCA conditions" organised by IAEA, Halden, Sept. 10-14, 2001, IAEA-TECDOC-1320
6. Mardon, J. P., Charquet, D., and Senevat, J., "Optimization of PWR Behavior of Stress-Relieved Zircaloy-4 Cladding Tubes by Upgrading the Manufacturing and Inspection Process," Zirconium in the Nuclear Industry: Tenth International Symposium, ASTM STP 1245, ASTM International, West Conshohocken, PA, pp. 329-348.
7. Mardon, J. P., Garner, G., Beslu, P., Charquet, D., and Senevat, J., "Update on the Development of Advanced Zr Alloys for PWR Fuel Rod Claddings," ANS International Topical Meeting on LWR Fuel Performance, Portland, March 2-6, 1997, pp. 405-412.
8. Mardon, J. P., Charquet, D., and Senevat, J., "Influence of Composition and Fabrication Process on Out-of-Pile and In-Pile Properties of M5 Alloy," Zirconium in the Nuclear Industry: Twelfth International Symposium, ASTM STP 1354, G. P. Sabol and G. D. Moan, Eds., ASTM International, West Conshohocken, PA, 2000, pp. 505-524.
9. Mardon, J. P., et al., "Recent Data on M5™ Alloy under LOCA Conditions," NRC Water Reactor Safety Meeting, Washington, DC, October 20-22, 2003.
10. Beck, L., de Château-Thierry, A., Frontier, J.-P., Pellegrino, S., Trouslard, Ph., "Twenty-five years of IBA Teaching Experience at the National Institute For Nuclear Science and Technology, France," Nucl. Instr. and Meth. B, in press.
11. Amsel, G. and Samuel, D., "Microanalysis of Stable Isotopes of Oxygen by Means of Nuclear Reactions," Analytical Chemistry 39, 14, 1689, 1967.
12. Amsel, G., Nadau, J.-P., d'Artemaere, E., David, D., Giraud, E., and Moulin, J., "Microanalysis by Direct Observation of Nuclear Reactions Using a 2 MeV Van de Graaff," Nucl. Instrum. and Meth. In Phys. Res. B92, 1971, p. 481.
13. Mayer, M., "SIMNRA User's Guide," Technical report IPP 9/113, Max-Plcmck-Institüt für Plasmaphysik, Garching, 1977.
14. Boehnmert, J., "Embrittlement of ZrNb1 at Room Temperature after High-Temperature Oxidation in Steam Atmosphere," Kerntechnik, 57, 1992, pp. 55-58.
15. Chung, H. M. and Kassner, T. F., "Embrittlement Criteria for Zircaloy Fuel Cladding Applicable to Accident Situations in Light-Water Reactors," NUREG/CR-1344, January 1980.
16. Hache, G. and Chung, H. M. "The History of LOCA Embrittlement Criteria," Proceedings of OCDE meeting on LOCA Fuel Safety Criteria, Aix-en-Provence, France, March 22-23, 2001, NEA/CSNI/R(2001)18.
17. Sundmann, B., Jansson, B., and Anderson, J. O. "The Thermo-Cal Databank System," Calphad, Vol. 9, No. 2, 1985, pp. 153-190.
18. Dupin, N., Ansara, I., Servant, C., Toffolon, C., Lemaignan, C., and Brachet, J. C., "A Thermodynamic Database for Zirconium Alloys," Journal of Nuclear Materials, Vol. 275, 1999, pp. 287-295.