Fe-13 Cr-Ti-Mo ferritic alloy as material for a fast reactor
- 30 September 1977
- journal article
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 68 (1) , 104-110
- https://doi.org/10.1016/0022-3115(77)90222-7
Abstract
No abstract availableKeywords
This publication has 3 references indexed in Scilit:
- The effect of a temperature change on void-swelling in electron-irradiated stainless steel type 316Journal of Nuclear Materials, 1976
- Dispersion-Strengthened Ferritic Steels as Fast-Reactor Structural MaterialsNuclear Technology, 1974
- The 885° f (475° c) embrittlement of ferritic stainless steelsMetallurgical Transactions, 1973