Hostname: page-component-78c5997874-dh8gc Total loading time: 0 Render date: 2024-11-18T15:01:31.912Z Has data issue: false hasContentIssue false

Radiation Growth of HCP Metals under Cascade Damage Conditions

Published online by Cambridge University Press:  13 February 2012

Stanislav I. Golubov
Affiliation:
Materials Science and Technology Division, ORNL, Oak Ridge, TN 37831- 6138, USA Center for Materials Processing, Department of Materials Science and Engineering, University of Tennessee, East Stadium Hall, Knoxville, TN 37996-0750, USA
Alexander V. Barashev
Affiliation:
Materials Science and Technology Division, ORNL, Oak Ridge, TN 37831- 6138, USA Center for Materials Processing, Department of Materials Science and Engineering, University of Tennessee, East Stadium Hall, Knoxville, TN 37996-0750, USA
Roger E. Stoller
Affiliation:
Materials Science and Technology Division, ORNL, Oak Ridge, TN 37831- 6138, USA
Get access

Abstract

Models of radiation growth proposed to date are all based on the assumption that the primary damage is produced by neutron irradiation in the form of single defects. These models do not account for the features of the cascade damage: intra-cascade clustering of self‑interstitial atoms (SIAs) and their one‑dimensional diffusion. During the last twenty years, a ‘Production Bias Model’ has been developed, which shows that the damage accumulation in cubic metals depends crucially on the cascade properties. The cascades in hcp zirconium are similar to those in cubic crystals; hence the model can provide a realistic framework for the hcp metals as well. In this work we present such a model in application to low-temperature (below 300°C) radiation growth.

Type
Research Article
Copyright
Copyright © Materials Research Society 2012

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

REFERENCES

1. Buckley, S.N., Properties of Reactor Materials and Effects of Radiation Damage, ed. Littler, W.J. (Butterworths, London, 1962) p. 413.Google Scholar
2. Holt, R.A., J. Nucl. Mater. 372, 182 (2008).Google Scholar
3. Wooding, S.J., Howe, L.M., Gao, F., Calder, A.F., and Bacon, D.J., J. Nucl. Mater. 254, 191 (1998).Google Scholar
4. De Diego, N., Osetsky, Y.N., and Bacon, D.J., In: Proceedings of MRS Fall Meeting; Boston, MA; USA; (2000) p. 200.Google Scholar
5. Holt, R.A., Woo, C.H., and Chow, C.K., J. Nucl. Mater. 205, 293 (1993).Google Scholar
6. Golubov, S.I., Singh, B.N., and Trinkaus, H., Phil. Mag. A81, 2533 (2001).Google Scholar
7. Walters, G.P., J. Nucl. Mater. 136, 263 (1985).Google Scholar
8. Wolfer, W.G., Computer-Aided Mater. Des. 14, 403 (2007).Google Scholar
9. Barashev, A.V., and Golubov, S.I., Phil. Mag. 89, 2833 (2009).Google Scholar
10. Singh, B.N., Golubov, S.I., Trinkaus, H., Serra, A., Osetsky, Yu.N., and Barashev, A.V., J. Nucl. Mater. 251, 107 (1997).Google Scholar
11. Golubov, S.I., Barashev, A.V., and Stoller, R.E.. “Mean Field Reaction Rate Theory”, In: Encyclopedia of Comprehensive Nuclear Materials, Chapter 1.13, edited by Konings, Rudy, Elsevier Ltd. (2012).Google Scholar
12. de Carlan, Y., Regnard, C., Griffiths, M., Gilbon, D., and Lemaignan, C., ASTM STP 1295, 638 (1996).Google Scholar
13. Griffiths, M., Holt, R.A., and Rogerson, A., J. Nucl. Mater. 225, 245 (1995).Google Scholar
14. Golubov, S.I., Barashev, A.V., and Stoller, R.E., ORNL Report ORNL/TM-2011/473 (2011), available online via http://www.osti.gov/bridge.Google Scholar
15. Holt, R.A., and Gilbert, R.W., J. Nucl. Mater. 116, 127 (1983).Google Scholar
16. Griffiths, M., J. Nucl. Mater. 159, 190 (1988).Google Scholar
17. Risbet, R., and Levy, V., J. Nucl. Mater. 50, 116 (1974).Google Scholar
18. Barashev, A.V., and Golubov, S.I., Phil. Mag. 90, 1787 (2010).Google Scholar