Hostname: page-component-8448b6f56d-c47g7 Total loading time: 0 Render date: 2024-04-23T13:50:11.427Z Has data issue: false hasContentIssue false
  • English
  • Français

Microstructure of V-4Cr-4Ti Following Low Temperature Neutron Irradiation

Published online by Cambridge University Press:  15 February 2011

P. M. Rice ,
L. L. Snead ,
D. J. Alexander  and
S. J. Zinkle
P. M. Rice
Affiliation:
Metals and Ceramics Division, Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 3783 1-6376
L. L. Snead
Affiliation:
Metals and Ceramics Division, Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 3783 1-6376
D. J. Alexander
Affiliation:
Metals and Ceramics Division, Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 3783 1-6376
S. J. Zinkle
Affiliation:
Metals and Ceramics Division, Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 3783 1-6376
Get access

Abstract

The V-4Cr-4Ti alloy displays excellent mechanical properties, including a ductile-to-brittle transition temperature (DBTT) below -200°C in the unirradiated condition. Specimens of this alloy were fission neutron-irradiated in the High Flux Beam Reactor (HFBR) at Brookhaven National Laboratory (BNL) to a dose of 0.4 dpa at temperatures from 100 to 275°C. Mechanical testing showed significant irradiation hardening in the alloy which increased with increasing irradiation temperature. Charpy impact testing also showed a dramatic increase in the DBTT on the order of 200 to 350°c. The mechanical property changes are correlated with preliminary results from the transmission electron microscopy (TEM) analysis of the defect microstructure resulting from the low-dose neutron irradiations. The TEM analysis of the irradiated material showed a nearly constant defect density of ∼1.6 × 1023 m−3, with an average defect diameter of slightly greater than 3 nm.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 439: Symposium B – Microstructure Evolution During Irradiation , 1996 , 343
Copyright
Copyright © Materials Research Society 1997

Access options

Get access to the full version of this content by using one of the access options below. (Log in options will check for institutional or personal access. Content may require purchase if you do not have access.)

References

1. Loomis, B. A. et al,. J. Nuclear Materials, 212–215, 799 (1994).Google Scholar
2. Alexander, D.J., Snead, L.L., Zinkle, S.J., Gubbi, A.N., Rowcliffe, A.F., and Bloom, E.E., in Fusion Materials Semiannual Progress Report for Period Ending June 30, 1996, DOE/ER-0313/20, p. 87, (1996).Google Scholar
3. Alexander, D.J., Snead, L.L., Zinkle, S.J., Gubbi, A.N., Rowcliffe, A.F., Eatherly, W.S., and Bloom, E.E., in Effects of Radiation on Materials: 18th International Symposium, ASTM STP 1325, edited by Nanstad, R.K., Hamilton, M.L., Garner, F.A., and Kumar, A. S., American Society for Testing and Materials, (1997) in press.Google Scholar
4. Grossbeck, M.L., et al., in Fusion Materials Semiannual Progress Report for Period Ending December 31, 1995, DOE/ER-0313/18, p. 183, (1995).Google Scholar
5. Staney, J.T. et al., Acta Met., 20, 191 (1972).Google Scholar
6. Hirsch, P., Howie, A., Nicholson, R, Pashley, D.W., and Whelan, M. J., Electron Microscopy of Thin Crystals, 2nd ed., Krieger Publishing Company, Malabar, Florida, pp. 509–511 (1977).Google Scholar
7. Kojima, S., Zinkle, S. J., and Heinisch, H.L., J. Nuclear Materials, 179–181, 982 (1991).Google Scholar
8. Belmont, A. L. Jr., in Strength of Metals and Alloys, Proc. of 2nd Int. Conf., ASM International, Metals Park, OH, p. 693 (1973).Google Scholar