Grain boundary segregation under electron irradiation in austenitic stainless steels modified with oversized elements
- 1 July 1992
- journal article
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 189 (2) , 167-174
- https://doi.org/10.1016/0022-3115(92)90529-t
Abstract
No abstract availableKeywords
This publication has 13 references indexed in Scilit:
- Radiation-induced grain boundary segregation and sensitization of a neutron-irradiated austenitic stainless steelPublished by Elsevier ,2003
- Radiation-induced segregation in binary and ternary alloysPublished by Elsevier ,2003
- Segregation of alloying elements to free surfaces during irradiationPublished by Elsevier ,2003
- Radiation-induced segregation and precipitation in Al-Zn alloysJournal of Nuclear Materials, 1989
- Solute segregation along non-migrated and migrated grain boundaries during electron irradiation in austenitic stainless steelsJournal of Nuclear Materials, 1987
- The role of phosphorus in the swelling and creep of irradiated austenitic alloysJournal of Nuclear Materials, 1985
- Radiation induced phosphorus segregation in austenitic and ferritic alloysJournal of Nuclear Materials, 1984
- Modeling crack growth processes in fusion reactor materialsJournal of Nuclear Materials, 1984
- Effect of minor alloying elements and their segregation on void suppression in modified 316 stainless steelsJournal of Nuclear Materials, 1984
- Effect of irradiation on phosphorus segregationJournal of Nuclear Materials, 1983