Ferritic steel-blanket systems integration R&D - Compatibility assessment

A. Kimura, R. Kasada, A. Kohyama, S. Konishi, M. Enoeda, M. Akiba, S. Jitsukawa, S. Ukai, T. Terai, A. Sagara

Research output: Contribution to journalConference articlepeer-review

18 Citations (Scopus)


The reduced activation ferritic steel (RAFS) has been selected as structural material for a variety of blanket systems for ITER test blanket modules (TBM). In the evaluation of integrated performance of ferritic steels as structural components of blanket systems, there are unique issues as well as common issues for each blanket system. One of the unique issues for each system is the compatibility of ferritic steels with the coolant materials. The corrosion rate of ferritic steels in hot water, super critical pressurized water (SCPW), humid air, Pb-17Li, lithium and Flibe at various temperatures is reviewed in this work. Efforts to improve corrosion resistance have been made, taking the alloy design into account. A dispersion of yttria was effective to improve corrosion resistance of a RAFS. The compatibilities of RAFSs with hot water, Pb-17Li, lithium and Flibe are considered to be good enough for the TBM applications. The liquid metal embrittlement (LME) is considered to be a critical issue for the utilization of RAFSs for the lithium systems. Several issues towards DEMO and beyond are shown from the compatibility point of view.

Original languageEnglish
Pages (from-to)909-916
Number of pages8
JournalFusion Engineering and Design
Issue number8-14 PART B
Publication statusPublished - 2006 Feb
EventProceedings of the Seventh International Symposium on Fusion Nuclear Technology ISFNT-7 Part B -
Duration: 2005 May 222005 May 27


  • Compatibility
  • Ferritic steels
  • Liquid metals
  • Salt
  • Test blanket modules
  • Water


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