Development of fabrication technology for low activation vanadium alloys as fusion blanket structural materials

Takuya Nagasaka, Takeo Muroga, Ken Ichi Fukumoto, Hideo Watanabe, Martin L. Grossbeck, Jiming Chen

研究成果: Contribution to journalArticle査読

27 被引用数 (Scopus)

抄録

Vanadium alloys, candidate fusion reactor blanket materials, consist of intrinsic low activation elements for 14 MeV fusion neutrons (e.g. vanadium, chromium and titanium). From 500 to 1000 K, the tensile strength of vanadium alloys is independent of temperature, enabling the fusion blanket to be operated at least 100 K higher than a blanket made from ferritic steel. However, most of the data have come from laboratory-scale fabricated vanadium alloy, so a feasibility study on large scale production of vanadium alloy products is required. In the present study, high-purity vanadium alloy products (e.g. plates, wires and tubes) were fabricated from reference high-purity V-4Cr-4Ti ingots designated as NIFS-HEAT, with the use of technologies applicable to industrial scale fabrication. A critical issue for NIFS-HEAT large-scale melting was to reduce the levels of interstitial impurities (e.g. C, N and O) that are known to deteriorate mechanical properties before and after neutron irradiation. Impurity behaviour during working and annealing processes and its effect on mechanical properties were investigated. Mechanical properties of the products were significantly improved by the control of Ti-C, N and O precipitation induced during the processes. Good mechanical properties comparable to laboratory-scale alloys were obtained at above 96% in cold working degree.

本文言語英語
ページ(範囲)618-625
ページ数8
ジャーナルNuclear Fusion
46
5
DOI
出版ステータス出版済み - 5 1 2006

All Science Journal Classification (ASJC) codes

  • 核物理学および高エネルギー物理学
  • 凝縮系物理学

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