Recent progress toward development of reduced activation ferritic/martensitic steels for fusion structural applications

R. J. Kurtz, Ana Alamo, E. Lucon, Q. Huang, S. Jitsukawa, A. Kimura, R. L. Klueh, G. R. Odette, C. Petersen, M. A. Sokolov, P. Spätig, J. W. Rensman

    Research outputpeer-review

    Abstract

    Significant progress has been achieved in the international research effort on reduced activation ferritic/martensitic steels for fusion structural applications. Because this class of steels is the leading structural material for test blankets in ITER and future fusion power systems, the range of ongoing research activities is extremely broad. Since, it is not possible to discuss all relevant work in this brief review, the objective of this paper is to highlight significant issues that have received recent attention. These include: (1) efforts to measure and understand radiation-induced hardening and embrittlement at temperatures ≤400 °C, (2) experiments and modeling to characterize the effects of He on microstructural evolution and mechanical properties, (3) exploration of approaches for increasing the high-temperature (>550 °C) creep resistance by introduction of a high-density of nanometer scale dispersoids or precipitates in the microstructure, (4) progress toward structural design criteria to account for loading conditions involving both creep and fatigue, and (5) development of nondestructive examination methods for flaw detection and evaluation.

    Original languageEnglish
    Pages (from-to)411-417
    Number of pages7
    JournalJournal of Nuclear Materials
    Volume386-388
    Issue numberC
    DOIs
    StatePublished - Apr 2009

    Funding

    This work was performed, in part, under the auspices of the US Department of Energy, Office of Fusion Energy Sciences, under Contract DE-AC06-76RLO1830.

    FundersFunder number
    U.S. Department of Energy
    U.S. Department of EnergyDE-AC06-76RLO1830

      ASJC Scopus subject areas

      • Nuclear and High Energy Physics
      • General Materials Science
      • Nuclear Energy and Engineering

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