Abstract
Residual grain-interaction stresses develop during the thermomechanical treatment of Zr alloys due to the anisotropy of the mechanical and thermal properties of the hep lattice. The origin and characteristics of this type of residual stress are described in conjunction with underlying physical principles employed to measure grain-interaction strains by means of neutron diffraction. The effect of thermal treatments, deformation, and irradiation on the evolution of residual grain-interaction strains are reviewed, and the most up-to-date experimental results are presented. The effects of grain-interaction stresses on the plasticity and in-reactor deformation of ZIRCALOY-2 will be discussed.
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V. Fidleris:Fundamental Mechanisms of Irradiation-Induced Creep and Growth, Proc. Int. Conf. Fundamental Mechanisms of Radiation-Induced Creep and Growth, C.H. Woo and R.J. McElroy, eds., North-Holland, Amsterdam, The Netherlands, 1988, pp. 22–42.
S.R. MacEwen, N. Christodoulou, C. Tomé, J. Jackman, T.M. Holden, J. Faber, Jr., and R.L. Hitterman:ICOTOM 8, Proc. 8th Int. Conf. on Texture of Materials, J.S. Kallend and G. Gottstein, eds., TMS, Warrendale, PA, 1988, pp. 825–36.
O.T. Woo, G.J.C. Carpenter, and S.R. MacEwen:J. Nucl. Mater., 1979, vol. 87, pp. 70–80.
N. Christodoulou:Acta Metall., 1989, vol. 37, pp. 529–39.
O.T. Woo: Chalk River Nuclear Laboratories, Atomic Energy of Canada Ltd., Chalk River, ON, Canada, unpublished research, 1989.
S.R. MacEwen, C. Tome, and J. Faber, Jr.:Acta Metall., 1989, vol. 37, pp. 979–89.
S.R. MacEwen, J. Faber, Jr., and A.P.L. Turner:Acta Metall., 1983, vol. 31, pp. 657–76.
S.R. MacEwen and C. Tome: ASTM STP 939, 1987, pp. 631–52.
D.L. Douglass:The Metallurgy of Zirconium, Atomic Energy Review Supplement 1971, International Atomic Energy Agency, Vienna, 1971, p. 8.
V. Perovic: Ontario Hydro Research, Toronto, ON, Canada, unpublished research, 1988.
R.G. Ballinger, G.E. Lucas, and R.M. Pelloux:J. Nucl. Mater., 1984, vol. 126, pp. 53–69.
B.E. Warren:X-Ray Diffraction, Addison-Wesley, Reading, MA, 1969, p. 264.
N. Christodoulou, S.R. MacEwen, J.F. Mecke, and O.T. Woo:Proc. 2nd Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, Monterey, CA, American Nuclear Society, La Grange Park, IL, 1985, pp. 515–22.
O.T. Woo and G.J.C. Carpenter:J. Nucl. Mater., 1988, vol. 159, pp. 397–404.
P. Chemelle, D.B. Knorr, J.B. Van de Sande, and R.B. Pelloux:J. Nucl. Mater., 1983, vol. 113, pp. 58–64.
S.N. Buckley:Properties of Reactor Materials and Effects of Irradiation Damage, D.J. Littler, ed., Butterworth’s, London, 1962, p. 41.
A. Salinas-Rodriguez, M.G. Akben, J.J. Jonas, and E.F. Ibrahim:Can. Metall. Q., 1985, vol. 24, pp. 259–72.
R.A. Holt and A.R. Causey:J. Nucl. Mater., 1987, vol. 150, pp. 306–18.
R.A. Holt, T.M. Holden, A.R. Causey, and V. Fidleris:Proc. 10th Risø Int. Symp. on Metallurgy and Materials Science: Materials Architecture, J.B. Bilde-Sørensen, N. Hansen, D. Juul Jensen, T. Leffers, H. Lilholt, and O.B. Pedersen, eds., Risø National Laboratory, Roskilde, Denmark, 1989, pp. 383–89.
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This paper is based on a presentation made in the symposium “Irradiation-Enhanced Materials Science and Engineering” presented as part of the ASM INTERNATIONAL 75th Anniversary celebration at the 1988 World Materials Congress in Chicago, IL, September 25–29, 1988, under the auspices of the Nuclear Materials Committee of TMS-AIME and ASM-MSD.
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MacEwen, S.R., Christodoulou, N. & Salinas-Rodríguez, A. Residual grain-interaction stresses in zirconium alloys. Metall Trans A 21, 1083–1095 (1990). https://doi.org/10.1007/BF02656529
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DOI: https://doi.org/10.1007/BF02656529