Interstitial loop nucleation and growth in solution-treated type 316 stainless steel irradiated to low doses with 22 MeV C2+ and 46.5 MeV Ni6+ ions
- 1 January 1979
- journal article
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 79 (1) , 28-42
- https://doi.org/10.1016/0022-3115(79)90431-8
Abstract
No abstract availableKeywords
This publication has 4 references indexed in Scilit:
- The void-swelling behaviour of solution-treated FV548 stainless steel irradiated with 22 MeV C2+ and 46.5 MeV Ni6+ ions and the influence of heat-treatmentJournal of Nuclear Materials, 1977
- The structure of fast-reactor irradiated solution-treated AISI type 316 steelJournal of Nuclear Materials, 1977
- Vacancy cluster damage in type 316 stainless steel irradiated with Cr+ ionsJournal of Nuclear Materials, 1975
- The dose dependence of void swelling in A.I.S.I. 316 stainless steel during 20 MeV C++ irradiation at 525 °CJournal of Nuclear Materials, 1971