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- Publisher
- Emerald Publishing
- Copyright
- Copyright © Emerald Group Publishing Limited
- ISSN
- 0003-5599
- DOI
- 10.1108/ACMM-11-2015-1611
- Publisher site
- See Article on Publisher Site
Abstract
PurposeThe liquid lithium-lead breeding blanket in the international thermonuclear experimental reactor is one of the major international concerns and one of the potential conceptual designs for the fusion reactor.Design/methodology/approachReduced activation ferritic-martensitic steels are being considered for application in future fusion technology as the relevant structural material, which will be in contact with the lithium-lead breeding material.FindingsAccording to the test results, comprehensive evaluations of these findings have been performed to determine the wastage rates and mechanisms for the conceptual design of the fusion reactor.Originality/valueFrom micro to macro, systematic cross-scale models are needed for the understanding of corrosion/wastage mechanisms in fusion reactor engineering applications.
Journal
Anti-Corrosion Methods and Materials – Emerald Publishing
Published: May 3, 2016