Abstract
The steady-state thermal creep rate in the axial and transverse directions of Zr-2.5Nb of pressure tubes, used in CANDU nuclear reactors, was determined. The data were obtained both from tensile samples having their tensile axes cut along the axial and transverse directions of the pressure tubes and from small-sized, thin-walled tubes, i.e., “mini” tubes stressed either in torsion or by internally pressurizing capsules manufactured from the mini tubes, or by additionally applying an external, axial load on these internally pressurized capsules. The temperature range of the data was from 373 to 596 K (100 °C to 323 °C) and the duration of the tests was from about 1500 hours to over 12,000 hours. The tests were carried out over a sufficiently long time for the creep rate to be measurable in the steady-state creep regime. It was found that the steady-state creep rate depends on stress in a nonlinear fashion and the stress exponent over the entire temperature range was about four. This value is consistent with the values measured earlier on other zirconium alloys. The activation energy Q was found to be about 21 and 10 kcal/mol for temperatures above and below 475 K (∼ 200 °C), respectively. These values are lower than those measured by other investigators on the same material at higher temperatures but similar to values found on other Zr alloys at low temperatures. It appears that Q is dependent on temperature and its value is consistent with the presence of dynamic strain aging (DSA). The results of this study were analyzed with a polycrystalline, nonlinear self-consistent model that take into account the crystallographic texture of the material. This model was used to derive the values of critical resolved shear stress (CRSS), which are consistent with prismatic, basal, and pyramidal glide. By using these values and the apparent temperature dependence of Q, it was shown that this model predicts well the steady-state creep rate over the entire temperature range and under very different stress states.
Similar content being viewed by others
References
V. Fidleris: J. Nucl. Mater., 1988, vol. 159, pp. 22–42.
R.A. Holt and R.G. Fleck: Zirconium in the Nuclear Industry: 9th Int. Symp., ASTM-STP-1132, ASTM, Philadelphia, PA, 1990, pp. 218–29.
R.A. Holt, A.R. Causey, and V. Fidleris: Proceedings, British Nuclear Society, London, 1983, pp. 175–78.
A.R. Causey, R.A. Holt, and S.R. MacEwen: Zirconium in the Nuclear Industry: 6th Int. Symp., ASTM-STP-824, ASTM, Philadelphia, PA, 1984, pp. 269–88.
R.A. Holt, M. Griffiths, and R.W. Gilbert: J. Nucl. Mater., 1987, vol. 149, pp. 51–56.
M. Griffiths: J. Nucl. Mater., 1988, vol. 159, pp. 190–218.
M. Griffiths, W. Phythian, and S. Dumbill: J. Nucl. Mater., 1993, vol. 207, pp. 353–56.
M. Griffiths, J.F. Mecke, and J.E. Winegar: Zirconium in the Nuclear Industry: 11th Int. Symp., ASTM-STP-1295, ASTM, West Conshohocken, PA, 1996, pp. 580–602.
R.G. Fleck, E.G. Price, and B.A. Cheadle: Zirconium in the Nuclear Industry: 6th Int. Symp., ASTM-STP-824, ASTM, Philadelphia, PA, 1984, pp. 88–105.
J.D. Parker, V. Perovic, M. Leger, and R.G. Fleck: Zirconium in the Nuclear Industry: 7th Int. Symp., ASTM-STP-939, ASTM, Philadelphia, PA, 1987, pp. 86–100.
D.D. Himbeault, C.K. Chow, and M.P. Puls: Metall. Mater. Trans. A, 1994, vol. 25A, pp. 135–45.
C.K. Chow, C.E. Coleman, M.H. Koike, A.R. Causey, C.E. Ells, R.R. Hosbons, S. Sagat, V.F. Urbanic, and D.K. Rodgers: Zirconium in the Nuclear Industry: 11th Int. Symp., ASTM STP 1295, ASTM, Philadelphia, PA, 1996, pp. 469–91.
B. Leitch, N. Christodoulou, and J. Root: Trans. 15th Int. Conf. on Structural Mechanics in Reactor Technology (SMiRT-15), Seoul, Korea, 1999, vol. XII, pp. 133–46.
A.R. Causey, V. Fidleris, S.R. MacEwen, and C.W. Schulte: Influence on Radiation on Material Properties: 13th Int. Symp. (Part II), ASTM STP 956, ASTM, Philadelphia, PA, 1988, pp. 54–68.
R.A. Holt: J. Nucl. Mater., 1976, vol. 59, pp. 234–42.
R.A. Holt and S.A. Aldridge: J. Nucl. Mater., 1985, vol. 135, pp. 246–59.
M. Griffiths, C.K. Chow, C.E. Coleman, R.A. Holt, S. Sagat, and V.F. Urbanic: Effects of Radiation on Materials, 16th Int. Symp., ASTM STP 1175, ASTM, Philadelphia, PA, 1996, pp. 1077–1110.
A.R. Causey, R.A. Holt, N. Christodoulou, and E.T.C. Ho: Zirconium in the Nuclear Industry: 12th Int. Symp., ASTM-STP 1354, ASTM, West Conshohocken, PA, 2000, pp. 74–85.
A.R. Causey, J.E. Elder, R.A. Holt, and R.G. Fleck: Zirconium in the Nuclear Industry: 6th Int. Symp., ASTM STP-1245, ASTM, Philadelphia, PA, 1994, pp. 202–20.
E.J. Hearn: in Mechanics of Materials, Pergamon Press, Elmsford, NY, 1977, vol. 1. published by the International Series of Materials Science and Technology, vol. 19, ed. H.G. Hopkins, pgs. 195–96.
N. Christodoulou, P.A. Turner, E.T.C. Ho, C.K. Chow, and M. Resta Levi: Metall. Mater. Trans. A, 2000, vol. 31A, pp. 409–19.
K.L. Murty, B.V. Tanikella, and J.C. Earthman: Acta Metall. Mater., 1994, vol. 42, pp. 3653–61.
V. Fidleris: J. Nucl. Mater., 1974, vol. 54, pp. 199–211.
R.D. Warda, V. Fidleris, and E. Tegtsoonian, Metall. Trans., 1973, vol. 4, pp. 1201–06.
V. Fidleris: Atomic Energy Rev., 1975, vol. 13, pp. 51–80.
V. Fidleris: Applications-Related Phenomena for Zirconium and Its Alloys, ASTM-STP-458, ASTM, Philadelphia, PA, 1969, pp. 1–17.
Creep of Zr Alloys in Nuclear Reactors, ASTM-STP-815, D.G. Franklin, G.E. Lucas, and A.L. Bement, eds., ASTM, Philadelphia, PA, 1983.
R.S.W. Shewfelt: Can. Metall. Q., 1984, vol. 23, pp. 441–45.
R.S.W. Shewfelt, L.W. Lyall, and D.P. Godin: J. Nucl. Mater., 1984, vol. 125, pp. 228–35.
M. Pahutova and J. Cadek: Kovove Mater., 1976, vol. 14, pp. 378–84.
M. Pahutova and J. Cadek: J. Nucl. Mater., 1976, vol. 61, pp. 285–96.
K. Nuttall: Scripta Metall., 1976, vol. 10, pp. 835–40.
M.J. Luton and J.J. Jonas: Can. Metall. Q., 1972, vol. 11, pp. 79–90.
M. Pahutova, K. Kucharova, and J. Cadek: Mater. Sci. Eng., 1977, vol. 27, pp. 239–48.
M. Pahutova and J. Cadek: Mater. Sci. Eng., 1975, vol. 20, pp. 277–85.
M. Pahutova and J. Cadek: J. Nucl. Mater., 1977, vol. 68, pp. 111–21.
I.M. Bernstein: Trans. TMS-AIME, 1967, vol. 239, pp. 1518–22.
Y.S. Kim: J. Nucl. Mater., 1997, vol. 250, pp. 164–70.
A. Akhtar: Acta Metall., 1973, vol. 21, pp. 1–11.
A. Akhtar: Metall. Trans. A, 1975, vol. 6A, pp. 1217–22.
B. Heritier, M.J. Luton, and J.J. Jonas: Met. Sci., 1974, vol. 8, pp. 41–48.
M. Davis, K.R. Montgomery, and J. Standring: J. Inst. Met., 1960–1961, vol. 89, pp. 172–74.
G. Beranger: Compt. Rend., 1964, vol. 259, pp. 4663–66.
H.E. Sills and R.A. Holt: Zirconium in the Nuclear Industry (4th Conf.), ASTM-STP-681, ASTM, Philadelphia, PA, 1979, pp. 325–41.
A. Akhtar: J. Nucl. Mater., 1973, vol. 47, pp. 79–86.
P.S. Follansbee and U.F. Kocks: Acta Metall., 1988, vol. 36, pp. 81–93.
H. Nakajima, G.M. Hood, and R.J. Schultz: Phil. Mag., 1988, vol. 58B, pp. 319–37.
A.D. King, G.M. Hood, and R.A. Holt: J. Nucl. Mater., 1991, vol. 185, pp. 174–81.
J. Horvath, F. Dyment, and H. Mehrer: J. Nucl. Mater., 1984, vol. 126, pp. 206–14.
Author information
Authors and Affiliations
Rights and permissions
About this article
Cite this article
Christodoulou, N., Chow, C.K., Turner, P.A. et al. Analysis of steady-state thermal creep of Zr-2.5Nb pressure tube material. Metall Mater Trans A 33, 1103–1115 (2002). https://doi.org/10.1007/s11661-002-0212-4
Received:
Issue Date:
DOI: https://doi.org/10.1007/s11661-002-0212-4