Creep of zirconium and zirconium alloys

Metallurgical and Materials Transactions A: Physical Metallurgy and Materials Science

Volumn 37, Issue 8, 2006, Pages 2389-2396

  Hayes, Troy A ^a   Kassner, Michael E ^b  

^a EXPONENT INC   (United States)

^b University of Southern California ^*  (United States)

Author keywords

[No Author keywords available]

Indexed keywords

ACTIVATION ENERGY; CREEP; IRRADIATION; OXYGEN; STRAIN RATE; STRESSES; TEMPERATURE; ZIRCONIUM;

CREEP STRENGTH; FIVE-POWER-LAW REGIME; ZIRCALOY;

ZIRCONIUM ALLOYS;

EID: 33747511388     PISSN: 10735623     EISSN: None     Source Type: Journal    
DOI: 10.1007/BF02586213     Document Type: Review

References (78)

1. R.C. Ecob and A.T. Donaldson: J. Nucl. Mater., 1985, vol. 132, pp. 110-25.
2. V. Fidleris: J. Nucl. Mater., 1968, vol. 26, pp. 51-76.
3. V. Fidleris and C.D. Williams: Electrochem. Technol., 1966, vol. 4, pp. 258-67.
4. A.J. Ardell and O.D. Sherby: Trans. TMS-AIME, 1967, vol. 239, pp. 1547-56.
5. E.R. Gilbert, S.A. Duran, and A.L. Bement: Applications-Related Phenomena for Zirconium and Its Alloys, ASTM STP 458, ASTM, Philadelphia, PA, 1968, pp. 210-25.
6. S.R. MacEwen, R.G. Fleck, E.T.C. Ho, and O.T. Woo: Metall. Trans. A, 1981, vol. 12A, pp. 1751-59.
7. M. Pahutova and J. Cadek: Mater. Sci. Eng., 1973, vol. 11, pp. 151-62.
8. I.M. Bernstein: Trans. TMS-AIME, 1967, vol. 239, pp, 1518-22.
9. B. Ramaswami and G.B. Craig: Trans. TMS-AIME, 1967. vol. 239, pp. 1226-31.
10. N. Prasad, G. Malakondaiah, and P. Rama Rao: Trans. Ind. Inst. Met., 1989, vol. 42 (supplement), pp. S165-74.
11. H. Siethoff and K. Ahlborn: Scripta Metall., 1987, vol. 21A, pp. 1439-44.
12. T.A. Hayes, M.E. Kassner, and R.S. Rosen: Metall. Mater. Trans. A, 2002, vol. 33A, pp. 337-43.
13. W. Blum and W. Maier: Phys. Status Solidi, 1999, vol. 171, pp. 467-74.
14. S. Fujishiro and D. Eylon: Scripta Metall., 1977, vol. 11, pp. 1011-16.
15. C. Quesne, C. Duong, F. Charpentier, J. Fries, and P. Lacombe: J. Less-Common Met., 1979, vol. 68, pp. 133-42.
16. S. Raff and R. Meyder: Water Reactor Fuel Element Performance Computer Modeling, Applied Science Publishers, London, 1983, p. 253.
17. S. Fujishiro and D. Eylon: Scripta Metall., 1977, vol. 11, pp. 1011-16.
18. M.E. Kassner and M.-T. Perez-Prado: Fundamentals of Creep in Metals and Alloys, Elsevier, Oxford, 2006.
19. M.T. Pérez-Prado, S.R. Barrabes, M.E. Kassner, and E. Evangelista: Acta Mater., 2005, vol. 53, pp. 581-91.
20. G.A. Henshall, M.E. Kassner, and H.J. McQueen: Metall. Mater. Trans. A, 1992, vol. A23, pp. 881-89.
21. M. Lubbehusen, K. Vieregge, G.M. Hood, H. Mehrer, and C. Herzig: J. Nucl. Mater., 1991, vol. 182, pp. 164-69.
22. J. Horvath, F. Dyment, and H. Mehrer: J. Nucl. Mater., 1984, vol. 126, pp. 206-14.
23. F. Dyment and C.M. Libanati: J. Mater. Sci., 1968, vol. 3, pp. 349-59.
24. G.B. Fedorov and F.I. Zhomov: Met. Metalloved. Chistyh. Metall., 1959, vol. 1, p. 161.
25. E.V Borisov, Yu. G. Godin, P.L. Gruzin, A.J. Evstyukhin, and V.S. Emel'yanov: Metall. Metallogr., 1958, p. 291.
26. V.S. Lyashenko, V.N. Bykov, and L.V. Pavlinov: Phys. Metall. Metallogr., 1959, vol. 8, pp. 40-46.
27. P. Flubacher: "Selbst-Diffusionsversuche in α-Zirkon," EIR-Bericht No. 49, Eidg. Institut für Reaktorforschung, Würenlingen, Switzerland, 1963.
28. G.M. Hood: Defect Diff. Forum, 1993, vols. 95-98, pp. 755-74.
29. W. Frank: Defect Diff. Forum, 1989, vols. 66-69, pp. 387-94.
30. E. Forlerer de Svarch and C. Rodriguez: J. Nucl. Mater., 1991, vol. 185, pp. 167-73.
31. T.A. Hayes: Ph.D. Dissertation, University of California, San Diego, CA, 2004.
32. J.J. Holmes: J. Nucl. Mater., 1964, vol. 13, pp. 137-41.
33. R.B. Jones: J. Nucl. Mater., 1966, vol. 19, pp. 204-07.
34. G. Kaspar, M. Peehs, E. Steinberg, and H. Schonfeld: Trans. 8th Int'L SMiRT Conf., North Holland, Amsterdam paper C1/8, 1985, pp. 51-7.
35. D.S. Wood and B. Watkins: J. Nucl. Mater., 1971, vol. 41, pp. 327-40.
36. K.M. Rose and E.D. Hindle: Zirconium in the Nuclear Industry, ASTM STP 633, ASTM, Philadelphia, PA, 1977, p. 24.
37. P.A. Ross-Ross and C.E.L. Hunt: J. Nucl. Mater., 1968, vol. 26, pp. 2-17.
38. B.D. Clay and G.B. Redding: "Creep Rupture Properties of Alpha-Phase Zircaloy Cladding Relevant to the Loss-of-Coolant Accident," CEGB Report No. RD/B/N 3187, 1975, Berkeley Nuclear Laboratories Report No. CEGB-RD/B/N 3782, Berkeley, England, 1976.
39. B.D. Clay and G.B. Redding: J. Br. Nucl. Ener. Soc., 1976, vol. 15, pp. 253-56.
40. N. Prasad, G. Malakondaiah, and P. Rama Rao: Scripta Metall., 1992, vol. 26, pp. 541-43.
41. N. Prasad, G. Malakondaiah, K. Muraleedharan, and P. Rama Rao: J. Nucl. Mater., 1988, vol. 158, pp. 30-41.
42. C.E. Coleman: J. Nucl. Mater., 1972, vol. 42, pp. 180-90.
43. B. Burton, A.T. Donaldson, and G.L. Reynolds: Zirconium in the Nuclear Industry, ASTM STP 681, ASTM, Philadelphia, PA, 1979, pp. 561-85.
44. G.E. Lucas and R.M.N. Pelloux: Nucl. Technol., 1981, vol. 53, pp. 46-57.
45. G.E. Lucas and R.M.N. Pelloux: Metall. Trans. A, 1981, vol. 12A, pp. 1321-31.
46. G.E. Lucas, M. Surprenant, J, DiMarzo, and G.J. Brown: J. Nucl. Mater., 1981, vol. 101, pp. 78-91.
47. P.J. Pankaskie: "Creep Properties of Zircaloy-2 for Design Application," HW-SA-2803, Hanford Atomic Products Operation, Richland, WA, 1962.
48. L.G. Bell: Can. Metall. Q., 1963, vol. 2, pp. 119-42.
49. F. Tinti: Nucl. Technol., 1983, vol. 60, pp. 104-13.
50. E.R. Gilbert and B. Mastel: ANS Trans., 1969, vol. 12, pp. 132-33.
51. Y. Matsuo: J. Nucl. Sci. Technol., 1987, vol. 24 (2), pp. 111-19.
52. F. Povolo and A.J. Marzocca: J. Nucl. Mater., 1981, vol. 97, pp. 323-32.
53. A.T. Donaldson and R.C. Ecob: Scripta Metall., 1985, vol. 19, pp. 1313-18.
54. C.C. Busby and K.B. Marsh: "High Temperature Time-Dependent Deformation in Internally Pressurized Zircaloy-4 Tubing (LBWR Development Program)," Bettis Atomic Power Laboratory Report No. WAPD-TM-1043, Westinghouse Electric Corporation, Pittsburgh, PA 1974.
55. C.C. Busby and L.S. White: "Some High Temperature Mechanical Properties of Internally Pressurized Zircaloy-4 Tubing," Bettis Atomic Power Laboratory Report No. WAPD-TM-1243, Westinghouse Electric Corporation, Pittsburgh, PA 1976.
56. A.M. Garde, H.M. Chung, and T.F. Kassner: Acta Metall., 1978, vol. 26, pp. 153-66.
57. A.M. Garde: J. Nucl. Mater, 1979, vol. 80, pp. 195-206.
58. H.M. Chung, A.M. Garde, and T.F. Kassner: "Mechanical Properties of Zircaloy Containing Oxygen," Argonne National Laboratory Report No. ANL-76-121, Argonne National Laboratory, Argonne, IL, 1978.
59. G. Brun, J. Pelchat, J.C. Floze, and M. Galimberti: Zirconium in the Nuclear Industry, ASTM STP 939, ASTM, Philadelphia, PA, 1987, pp. 597-616.
60. M. Mayuzumi and T. Onchi: J. Nucl. Mater., 1990, vol. 175, pp. 135-42.
61. M. Mayuzumi and T. Onchi: J. Nucl. Mater., 1990, vol. 171, pp. 381-88.
62. K.L. Murty: JOM, 1999, vol. 51, pp. 32-39.
63. K.L. Murty, B.V. Tanikella, and J.C. Earthman: Acta Metall. Mater, 1994, vol. 42, pp. 3653-61.
64. K.L. Murty: Trans. Ind. Inst. Met., 2000, vol. 53, pp. 107-20.
65. Y.-S. Kim: J. Nucl. Mater., 1997, vol. 250, pp. 164-70.
66. J.H. Choe and J.H. Hong: J. Kor. Inst. Met., 1984, vol. 22, pp. 613-20.
67. Y.-K. Park, T.-S. Kim, J.-H. Choi, and M.-Y. Wee: J. Kor. Inst. Met. Mater., 2000, vol. 38, pp. 624-28.
68. H.E. Rosinger, P.C. Bera, and W.R. Clendening: "The Steady State Creep of Zircaloy-4 Fuel Cladding from 940 to 1873 K," AECL-6193, Atomic Energy of Canada Limited, Whiteshell Nuclear Research Establishment, Pinawa, Manitoba, Canada, 1978.
69. G. Porsch, J. Fleisch, and B. Heits: Nucl. Technol., 1986, vol. 74, pp. 287-98.
70. M. Peehs and J. Fleisch: J. Nucl. Mater., 1986, vol. 137, pp. 190-202.
71. R.E. Einziger, H. Tsai, M.C. Billone, and B.A. Hilton: "Examination of Spent Fuel Rods after 15 Years in Dry Storage," Report No. NUREG/ CR-6831, ANL-03/17, Argonne National Laboratory, Argonne, IL, 2003.
72. R.E. Einziger, S.D. Atkin, D.E. Stellrecht, and V. Pasupathi: Nucl. Technol., 1982, vol. 57, pp. 65-80.
73. R.E. Einziger and R. Kohli: Nucl. Technol., 1984, vol. 67, pp. 107-23.
74. W. Goll, H. Spilker, and E. Toscano: J. Nucl. Mater., 2001, vol. 289, pp. 247-53.
75. C. Pescatore and M.G. Cowgill: "Temperature Limit Determination for the Inert Dry Storage of Spent Nuclear Fuel - Final Report," EPRI TR-103949, Brookhaven National Laboratory, Upton, NY, 1994.
76. P.J. Henningson, J.T. Willse, B. Cox, M.G. Bale, K.L. Murty, and W.A. Pavinich: "Cladding Integrity under Long Term Disposal," Framatome Technologies Report No. 51-1267509-00, 1998.
77. R.L. Keusseyan, C.P. Hu, and C.Y. Li: J. Nucl. Mater., 1979, vol. 80, pp. 390-92.
78. T.A. Hayes, R.S. Rosen, and M.E. Kassner: J. Nucl. Mater., in press.