Calculated Phase Diagram for Zirconium-Oxygen-Hydrogen Ternary System

Transactions of the Atomic Energy Society of Japan

Volumn 2, Issue 4, 2003, Pages 452-459

  Setoyama, Daigo ^a   Yamanaka, Shinsuke ^a  

^a OSAKA UNIVERSITY   (Japan)

Author keywords

calculated phase diagrams; CALPHAD; hydrogen; oxygen; thermodynamics; zirconium

Indexed keywords

EID: 85010588926     PISSN: 13472879     EISSN: 21862931     Source Type: Journal    
DOI: 10.3327/taesj2002.2.452     Document Type: Article

References (28)

1. Y. Ashida, M. Yamamoto, S. Naito, M. Mabuchi, “Measurements of Young's modulus and the modulus of rigidity of the solid solution of hydrogen in zirconium between 300 and 1300 K,” J. Appl. Phys., 80[6], 3254(1996).
2. I. G. Ritchie, Z. L. Pan, “Internal friction and Young's modulus measurements in Zr-2.5Nb alloy doped with hydrogen,” ASTM-STP 1169, 385(1992).
3. Z. L. Pan, I. G. Ritchie, M. P. Puls, “The terminal solid solubility of hydrogen and deuterium in Zr-2.5Nb alloys,” J. Nucl. Mater., 228, 227(1996).
4. Z. L. Pan, M. P. Puls, I. G. Ritchie, “Measurement of hydrogen solubility during isothermal charging in a Zr alloy using an internal friction technique,” J. Alloys Comp., 211/212, 245 (1994).
5. S. Yamanaka, K. Yoshida, M. Uno, M. Katsura, H. Anada, T. Matsuda, S. Kobayashi, “Thermal and mechanical properties of zirconium hydride,” J. Alloys Comp., 293–295, 3(1999).
6. M. Kuroda, K. Yoshida, S. Yamanaka, H. Anada, F. Nagase, H, Uetsuka, “Influence of precipitated hydride on the fracture behavior of zircaloy fuel cladding tube,” J. Nucl. Sci. Technol., 37, 670(2000).
7. M. Kuroda, S. Yamanaka, F. Nagase, H. Uetsuka, “Analysis of the fracture behavior of hydrided fuel cladding by fracture mechanics,” Nucl. Eng. Des., 203, 185(2001).
8. S. Yamanaka, M. Kuroda, D. Setoyama, M. Uno, K. Takeda, H. Anada, F. Nagase, H. Uetsuka, “Analysis of the fracture behavior of a hydrided cladding tube by fracture mechanics,” J. Alloys Comp., 330–332, 400 (2002).
9. M. Kuroda, S. Yamanaka, D. Setoyama, M. Uno, K. Takeda, H. Anada, F. Nagase, H. Uetsuka, “Tensile test of hydrided Zircaloy,” J. Alloys Comp., 330–332, 404 (2002).
10. M. Kuroda, S. Yamanaka, “Assessment of the combined effects of irradiation and hydrogenation on the fracture behavior of Zircaloy fuel claddings by fracture mechanics,” J. Nucl. Sci. Technol., 39[3], 234 (2002).
11. H. Stehle, W. Kaden, R. Manzel, “External corrosion of cladding in PWRs,” Nucl. Eng. Des., 33, 155 (1975).
12. B. Cox, “A mechanism for the hydrogen uptake process in zirconium alloys,” J Nucl. Mater., 264, 283 (1999).
13. P. Rudling, G. Wikmark, “A unified model of Zircaloy BWR corrosion and hydriding mechanisms,” J. Nucl. Mater., 265, 44 (1999).
14. T. B. Massalski, Binary Alloy Phase Diagrams, Vol. 3., ASM, Ohio, 2940 (1992).
15. T. B. Massalski, Binary Alloy Phase Diagrams, Vol. 2., ASM, Ohio, 2078 (1992).
16. S. Yamanaka, T. Tanaka, M. Miyake, “Effect of oxygen on hydrogen solubility in zirconium,” J. Nucl. Mater., 167, 231 (1989).
17. S. Yamanaka, M. Miyake, M. Katsura, “Study on the hydrogen solubility in zirconium alloys,” J. Nucl. Mater., 247, 315 (1997).
18. N. Dupin, I. Ansara, C. Servant, C. Toffolon, C. Lemaignan, J. C. Brachet, “A thermodynamic database for zirconium alloys,” J Nucl. Mater., 275, 287 (1999).
19. P. Liang, N. Dupin, S. G. Fries, H. J. Seifert, I. Ansara, H. L. Lukas, F. Aldinger, “Thermodynamic assessment of the Zr-O binary system,” Z. Metallkd., 92[7], 747(2001).
20. M. Hillert, Phase Equilibria, Phase Diagrams and Phase Transformations, Cambridge University Press, UK, 143 (1998).
21. N. Saunders, A. P. Miodownik, Calphad, Pergamon, UK, 17 (1998).
22. A. T. Dinsdale, “SGTE data for pure elements,” Calphad, 15 [4], 317 (1991).
23. M. Hillert, L. I. Staffanson, “The regular solution model for stoichiometric phases and ionic melts,” Acta Chem. Scand., 24, 3618 (1970).
24. O. Redlich, A. Kister, Ind. Eng. Chem., 40, 345 (1948).
25. S. Yamanaka, T. Nishizaki, M. Uno, M. Katsura, “Hydrogen dissolution into zirconium oxide,” J. Alloys Comp., 293–295, 38 (1999).
26. P. Y. Chevalier, E. Fischer, “Thermodynamic modelling of the O-U-Zr system,” J. Nucl. Mater., 257, 213 (1998).
27. R. Arroyave, L. Kaufman, T. W. Eager, “Thermodynamic modeling of the Zr-O system,” Calphad, 26[1], 95 (2002).
28. K. Komatsu, Y. Takada, M. Mizuta, S. Takahashi, “The effects of oxidation temperature and slow-cooldown on ductile-brittle behavior of zircaloy fuel cladding,” Proc. Special Mtg. on the Behavior of Water Reactor Fuel Elements under Accident Conditions, Spatind, Norway, Sept. 13–16 (1976).