Significant differences in defect accumulation behaviour between fcc and bcc crystals under cascade damage conditions
- 1 November 1995
- journal article
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 226 (3) , 277-285
- https://doi.org/10.1016/0022-3115(95)00121-2
Abstract
No abstract availableThis publication has 36 references indexed in Scilit:
- Defect accumulation in pure fcc metals in the transient regime: a reviewPublished by Elsevier ,2003
- Microstructure and mechanical behaviour of TZM and Mo-5% Re alloys irradiated with fission neutronsJournal of Nuclear Materials, 1995
- Defect microstructure in copper alloys irradiated with 750 MeV protonsJournal of Nuclear Materials, 1994
- Saturation of swelling in neutron-irradiated molybdenum and its dependence on irradiation temperature and starting microstructural stateJournal of Nuclear Materials, 1994
- Impact of glissile interstitial loop production in cascades on defect accumulation in the transientJournal of Nuclear Materials, 1993
- Experimental studies of cascade phenomena in metalsJournal of Nuclear Materials, 1993
- Correlation of interstitials within defect cascades in Al(Zn) and Cu observed by diffuse X-Ray scatteringJournal of Nuclear Materials, 1989
- Some implications of anisotropic self-interstitial diffusion on void swelling in metalsJournal of Nuclear Materials, 1985
- Fluence and flux dependence of void formation in pure aluminumJournal of Nuclear Materials, 1971
- Voids in vanadium, niobium and molybdenum by fast neutron irradiation at high temperaturesJournal of Nuclear Materials, 1971