Technical issues of reduced activation ferritic/martensitic steels for fabrication of ITER test blanket modules

H. Tanigawa, T. Hirose, K. Shiba, R. Kasada, E. Wakai, H. Serizawa, Y. Kawahito, S. Jitsukawa, A. Kimura, Y. Kohno, A. Kohyama, S. Katayama, H. Mori, K. Nishimoto, R. L. Klueh, M. A. Sokolov, R. E. Stoller, S. J. Zinkle

Research output: Contribution to journalArticlepeer-review

79 Citations (Scopus)

Abstract

Reduced activation ferritic/martensitic steels (RAFMs) are recognized as the primary candidate structural materials for fusion blanket systems. The RAFM F82H was developed in Japan with emphasis on high-temperature properties and weldability. Extensive irradiation studies have conducted on F82H, and it has the most extensive available database of irradiated and unirradiated properties of all RAFMs. The objective of this paper is to review the R&D status of F82H and to identify the key technical issues for the fabrication of an ITER test blanket module (TBM) suggested from the recent research achievements in Japan. This work clarified that the primary issues with F82H involve welding techniques and the mechanical properties of weld joints. This is the result of the distinctive nature of the joint caused by the phase transformation that occurs in the weld joint during cooling, and its impact on the design of a TBM will be discussed.

Original languageEnglish
Pages (from-to)1471-1476
Number of pages6
JournalFusion Engineering and Design
Volume83
Issue number10-12
DOIs
Publication statusPublished - 2008 Dec 1
Externally publishedYes

Keywords

  • F82H
  • Fabrication
  • HAZ
  • Irradiation effect
  • Over-tempered HAZ
  • RAFM
  • TBM
  • WCSB
  • Weld

ASJC Scopus subject areas

  • Civil and Structural Engineering
  • Nuclear Energy and Engineering
  • Materials Science(all)
  • Mechanical Engineering

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