Development of an oxide dispersion strengthened, reduced-activation steel for fusion energy
- 27 November 2000
- journal article
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 283-287, 642-646
- https://doi.org/10.1016/s0022-3115(00)00137-9
Abstract
No abstract availableKeywords
This publication has 4 references indexed in Scilit:
- Alloying design of oxide dispersion strengthened ferritic steel for long life FBRs core materialsPublished by Elsevier ,2003
- Current status and future R&D for reduced-activation ferritic/martensitic steelsJournal of Nuclear Materials, 1998
- Development of Oxide Dispersion Strengthened Steels for FBR Core Application, (II)Journal of Nuclear Science and Technology, 1998
- Fabrication and Mechanical Properties of Oxide Dispersion Strengthening Ferritic Alloy Canning Tubes for Fast Reactor Fuel PinsNuclear Technology, 1985