Recent status and improvement of reduced-activation ferritic-martensitic steels for high-temperature service

L. Tan, Y. Katoh, A. A.F. Tavassoli, J. Henry, M. Rieth, H. Sakasegawa, H. Tanigawa, Q. Huang

Research output: Contribution to journalReview articlepeer-review

103 Scopus citations

Abstract

Reduced-activation ferritic-martensitic (RAFM) steels, candidate structural materials for fusion reactors, have achieved technological maturity after about three decades of research and development. The recent status of a few developmental aspects of current RAFM steels, such as aging resistance, plate thickness effects, fracture toughness, and fatigue, is updated in this paper, together with ongoing efforts to develop next-generation RAFM steels for superior high-temperature performance. In addition to thermomechanical treatments, including nonstandard heat treatment, alloy chemistry refinements and modifications have demonstrated some improvements in high-temperature performance. Castable nanostructured alloys (CNAs) were developed by significantly increasing the amount of nanoscale MX (M = V/Ta/Ti, X = C/N) precipitates and reducing coarse M23C6 (M = Cr). Preliminary results showed promising improvement in creep resistance and Charpy impact toughness. Limited low-dose neutron irradiation results for one of the CNAs and China low activation martensitic are presented and compared with data for F82H and Eurofer97 irradiated up to ∼70 displacements per atom at ∼300–325 °C.

Original languageEnglish
Pages (from-to)515-523
Number of pages9
JournalJournal of Nuclear Materials
Volume479
DOIs
StatePublished - Oct 1 2016

Funding

This research was supported by the U.S. Department of Energy , Office of Science , Fusion Energy Sciences . This manuscript was authored by UT-Battelle, LLC, under contract number DE-AC05-00OR22725 with the U.S. Department of Energy . Part of this work was supported by the EUROfusion Consortium through the Euratom research and training programme, “Broader Approach Agreement” between the Government of Japan and the Euratom, and the National Basic Research Program of China. The authors thank F.W. Wiffen and S.J. Zinkle for useful discussions.

FundersFunder number
Eurofusion consortium
U.S. Department of Energy
Office of Science
Fusion Energy SciencesDE-AC05-00OR22725
Horizon 2020 Framework Programme633053
H2020 Euratom
National Basic Research Program of China (973 Program)

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