Effect of irradiation on failure mode during creep
Mechanical Behavior
Received:
- 33 Downloads
- 6 Citations
Abstract
In-reactor stress to rupture results in excess of 11,000 hours are reported. Stress rupture properties during in-reactor testing of AISI 316 CW were demonstrated to be greater than or equal to the unirradiated material properties. Failure strains of the pressurized tube specimens were found to be stress dependent with a minimum in failure strain occurring at 200 MPa for unirradiated tests. Higher failure strains at lower stresses resulted from a transition in crack propagation mechanisms from triple point wedge cracking to grain boundary cavitation. The triple point cracking to cavitation transition was shifted to lower stresses by irradiation.
Keywords
Heat Pipe Triple Point Failure Strain Rupture Life Tertiary Creep
These keywords were added by machine and not by the authors. This process is experimental and the keywords may be updated as the learning algorithm improves.
Preview
Unable to display preview. Download preview PDF.
References
- 1.E. L. Robinson:Trans. ANS, 1952, vol. 74, p. 777.Google Scholar
- 2.A. J. Lovell and J. J. Holmes:Trans. ANS, 1972, vol. 15–2, p. 735.Google Scholar
- 3.N. E. Hinkle: ASTM STP 341, 1963, p. 344.Google Scholar
- 4.J. A. Williams and J. W. Carter: ASTM STP 426, 1968, p. 149.Google Scholar
- 5.E. R. Gilbert and N. E. Harding: ASTM STP 457, 1969, p. 17.Google Scholar
- 6.A. J. Lovell:Trans. ANS, 1969, vol. 12, p. 127.Google Scholar
- 7.E. E. Bloom and J. O. Stiegler:Nuclear Tech., 1973, vol. 17, p. 24.Google Scholar
- 8.M. Weiss, J. Malkin, J. Erler, and J. P. Andre: ASTM STP 457, 1969, p. 352.Google Scholar
- 9.E. E. Bloom and J. O. Stiegler: ASTM STP 529, 1973, p. 360.Google Scholar
- 10.J. J. Holmes, A. J. Lovell, and R. L. Fish: ASTM STP 529, 1973, p. 383.Google Scholar
- 11.A. J. Lovell:Nuclear Tech., 1975, vol. 26, p. 297.Google Scholar
- 12.J. M. Dupouy, J. Erler, and R. Huillery:Radiation Effects in Breeder Reactor Structural Materials, AIME, 1977, p. 83.Google Scholar
- 13.J. Barnaby, P. H. Bargon, R. M. Boothly, A. S. Fraser, and F. G. Slattery:Radiation Effects in Breeder Reactor Structural Materials, AIME, 1977, p. 159.Google Scholar
- 14.E. R. Gilbert and J. F. Bates:J. of Nuc. Mat'ls., 1977, vol. 65, p. 204.CrossRefGoogle Scholar
- 15.E. R. Gilbert and L. D. Blackburn:J. of Eng. Materials, 1977, vol. 99, p. 168.Google Scholar
- 16.A. J. Lovell, B. A. Chin, and E. R. Gilbert:Journal of Materials Science, 1981, vol. 16, p. 870.CrossRefGoogle Scholar
- 17.M. M. Paxton, B. A. Chin, E. R. Gilbert, and R. E. Nygren:J. of Nuc. Mat'ls., 1979, vol. 80, p. 144.CrossRefGoogle Scholar
- 18.E. R. Gilbert and B. A. Chin:Nuclear Tech., 1981, vol. 52, p. 273.Google Scholar
- 19.E. R. Gilbert and B. A. Chin: “Effects of Radiation on Materials: Tenth Conference”, ASTM STP 725, 1981, p. 665.Google Scholar
- 20.D. G. Franklin and W. E. Ruther:Trans. ANS, Nov. 2, 1971, vol. 14, p. 632.Google Scholar
Copyright information
© The Metallurgical of Society of AIME 1987