Influence of hydrogen content on the α/β phase transformation temperatures and on the thermal-mechanical behavior of Zy-4, M4 (ZrSnFeV), and M5™ (ZrNbO) alloys during the first phase of LOCA transient

ASTM Special Technical Publication

Volumn , Issue 1423, 2002, Pages 673-700

  Brachet, Jean Christophe ^a   Portier, Laurence ^a   Forgeron, Thierry ^a   Hivroz, Jacky ^a   Hamon, Didier ^a   Guilbert, Thomas ^a   Bredel, Thierry ^a   Yvon, Pascal ^a   Mardon, Jean Paul ^b   Jacques, Patrick ^c  

^a SRMA   (France)

^b AREVA NP   (France)

^c EDF R AND D   (France)

Author keywords

Alpha to beta phase transformation; Creep; Hydrogen effect; LOCA; M4 ZrSnFeV; M5 ZrNbo; Zirconium alloy; Zy 4

Indexed keywords

CLADDING (COATING); COMPUTER SIMULATION; CREEP TESTING; DEFORMATION; HYDROGEN; LOSS OF COOLANT ACCIDENTS; METALLURGY; PHASE TRANSITIONS;

ALPHA TO BETA PHASE TRANSFORMATION; HYDROGEN EFFECT; M4-ZRSNFEV; M5-ZRNBO; THERMAL-MECHANICAL BEHAVIOR; ZY-4;

ZIRCONIUM ALLOYS;

EID: 8844262007     PISSN: 00660558     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (24)

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., American Society for Testing and Materials, Philadelphia, 1987, pp. 451-488.
2. Forgeron, T., Brachet, J.-C., Barcelo, F., Castaing, A., Hivroz, J., Mardon, J.-P., and Bernaudat, C., "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., American Society for Testing and Materials, West Conshohocken, PA, 2000, pp. 256-278.
3. 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," ASTM STP 1245, pp. 329-348.
4. 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 Portland, Vol. 2, 6/03/1997, pp. 405-412.
5. 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., American Society for Testing and Materials, West Conshohocken, PA, 2000, pp. 505-524.
6. Couterne, J.C. and Cizeron, G., Journal of Nuclear Materials, Vol. 20, 1966, p. 79.
7. Brachet J. C., Béchade, J.-L., Castaing, A., Le Blanc, L., and Jouen, T., "Relationship between Crystallographic Texture and Dilatometric Behavior of a Hexagonal Polycrystalline Material," Materials Science Forum, Trans Tech Publications, Switzerland, Vols. 273-275, 1998, pp. 529-534.
8. Réocreux, M. and Scott de Martinville, E., "A Study of Fuel Behavior in PWR Design Basis Accident: An Analysis of the Results from PHEBUS and EDGAR Experiments," Nuclear Engineering and Design, Vol. 124, No. 3, 1990, pp. 363-378.
9. Kearns, J. J., "Terminal Solubility and Pardoning of Hydrogen in the Alpha Phase of Zirconium, Zircaloy-2 and Zircaloy-4," Journal of Nuclear Materials, Vol. 22, 1967.
10. McMinn, A., Darby, E. C., and Schofield, J. S., "The Terminal Solid Solubility of Hydrogen in Zirconium Alloys," Zirconium in the Nuclear Industry: Twelfth International Symposium, ASTM STP 1354, G. P. Sabol and G. D. Moan, Eds., American Society for Testing and Materials, West Conshohocken, PA, 2000, pp. 173-195.
11. Khatamian, D., Pan, Z. L., Puls, M. P., and Cann, C. D., "Hydrogen Solubility Limits in Excel, an Experimental Zirconium-Based Alloy," Journal of Alloys and Compounds, Vol. 231, 1995, pp. 488-493.
12. Slattery, G. F., "The Terminal Solubility of Hydrogen in Zirconium Alloys between 30 and 400°C," Journal of The Institute of Metals, Vol. 95, 1967, pp. 43-47.
13. Espagno, L., Azou, P., and Bastien, P., "Variations de longueur et de densité accompagnant le chargement en hydrogène du zirconium," Comptes Rendus à l'Académie des Sciences, Vol. 247, 1958, pp. 83-86.
14. Erickson, W. H. and Hardie, D., "The Influence of Alloying Elements on the Terminal Solubility of Hydrogen in a-Zirconium," Journal of Nuclear Materials, Vol. 13, No. 2, 1964, pp. 254-262.
15. Espagno, L., Azou, P., and Bastien, P., "Etude dilatométrique entre l'ambiante et 550°C du système zirconium-hydrogène, " Comptes Rendus à l'Académie des Sciences, Vol. 248, 1959, pp. 2003-2005.
16. Bouffioux, P. and Rupa, N., "Impact of Hydrogen on Plasticity and Creep of Unirradiated Zircaloy-4 Cladding Tubes," Zirconium in the Nuclear Industry: Twelfth International Symposium, ASTM STP 1354, G. P. Sabol and G. D. Moan, Eds., American Society for Testing and Materials, West Conshohocken, PA, 2000, pp. 399-422.
17. Pilvin, P., "Identification des paramètres de modèles de comportement," Proceedings, Mecamat, Besançon, France, 1988, p. 155.
18. Fréchinet, S., Ph.D. thesis work, Centre des Matériaux de l'Ecole des Mines de Paris, to be published.
19. Johnson, W. A. and Mehl R. F., "Reaction Kinetics in Processes of Nucleation and Growth," Transactions of AIME, Vol. 135, February 1939, p. 416.
20. Avrami, M., "Kinetics of Phase Change I-General Theory," Journal of Chemistry and Physics, Vol. 7, December 1939, p. 1103.
21. Kolmogorov, A. N., Izv. Akad. Nauk. SSSR., Vol. 3, 1937, p. 355.
22. Holt, R. A., Sills, H. E., and Sagat, S., Proceeding of the IAEA Specialists Meeting, IGWGFPT/7, Blackpool, U.K., 1980.
23. Bocek, M., Hofmann, P., and Petersen, C., "Superplasticity of Zircaloy-4," Zirconium in the Nuclear Industry, ASTM STP 633, 1977, pp. 66-81.
24. Garde, A. M., Chung, H. M., and Kassner, T. F., "Micrograin Superplasticity in Zircaloy at 850°C," Acta Metallurgica, Vol. 26, January 1978, pp. 153-166.