Development of next generation tempered and ODS reduced activation ferritic/martensitic steels for fusion energy applications

S. J. Zinkle, J. L. Boutard, D. T. Hoelzer, A. Kimura, R. Lindau, G. R. Odette, M. Rieth, L. Tan, H. Tanigawa

Research output: Contribution to journalArticlepeer-review

222 Scopus citations

Abstract

Reduced activation ferritic/martensitic steels are currently the most technologically mature option for the structural material of proposed fusion energy reactors. Advanced next-generation higher performance steels offer the opportunity for improvements in fusion reactor operational lifetime and reliability, superior neutron radiation damage resistance, higher thermodynamic efficiency, and reduced construction costs. The two main strategies for developing improved steels for fusion energy applications are based on (1) an evolutionary pathway using computational thermodynamics modelling and modified thermomechanical treatments (TMT) to produce higher performance reduced activation ferritic/martensitic (RAFM) steels and (2) a higher risk, potentially higher payoff approach based on powder metallurgy techniques to produce very high strength oxide dispersion strengthened (ODS) steels capable of operation to very high temperatures and with potentially very high resistance to fusion neutron-induced property degradation. The current development status of these next-generation high performance steels is summarized, and research and development challenges for the successful development of these materials are outlined. Material properties including temperature-dependent uniaxial yield strengths, tensile elongations, high-temperature thermal creep, Charpy impact ductile to brittle transient temperature (DBTT) and fracture toughness behaviour, and neutron irradiation-induced low-temperature hardening and embrittlement and intermediate-temperature volumetric void swelling (including effects associated with fusion-relevant helium and hydrogen generation) are described for research heats of the new steels.

Original languageEnglish
Article number092005
JournalNuclear Fusion
Volume57
Issue number9
DOIs
StatePublished - Jun 9 2017

Funding

This work was supported in part by the Office of Fusion Energy Sciences, U.S. Department of Energy. Part of this work, supported by the European Commission under the contract of Associations, was carried out within the framework of the European Fusion Development Agreement. The views and opinions expressed herein do not necessarily reflect those of the European Commission. The authors thank D. Stork and G. Federici for useful discussions.

Keywords

  • ductility
  • fracture toughness
  • point defect sink strength
  • radiation effects
  • thermal creep strength
  • void swelling
  • yield strength

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