Present Status of High Z Material Development(<Special Topic Articles>Application of High Z Materials as a Plasma Facing Material)
Bibliographic Information
- Other Title
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- 高Z材料の開発状況
- コウ Z ザイリョウ ノ カイハツ ジョウキョウ
- 5.高Z材の開発状況(<小特集>プラズマ対向壁としての高Z材)
- 高Z材料の開発状況
- 小特集 プラズマ対向壁としての高Z材
- ショウ トクシュウ プラズマ タイコウヘキ トシテノ コウ Zザイ
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Abstract
Tungsten (W) is selected as high-Z divertor material for ITER, because of high threshold energy of self-sputtering, high recycling yield and low disruption yield. CVD-W, which has very high purity and small grain structures, has been developed at JAERI, and physical and mechanical properties such as thermal conductivity and tensile strength have been measured. Disruption erosions of CVD-W, monocrystal-W and powder sintered W have been also measured under 2 GW/m^2 for 2 ms with JAERl Electron Beam Irradiation System. In result, the erosion of CVD-W was smaller than that of the other W. Small divertor mock-ups were fabricated with CVD-W and its thermal fatigue tests was performed under equivalent conditions of 5 MW/m^2 for steady state. In result, CVD-W Iayer was survived on the heat sink after 1000 thermal cycles. Neutron irradiation of CVD-W is ongoing in JAERI Material Test Reactor. Subjects to be developed on CVD-W are wider coating, thicker coating, coating on a curved surface, coating on CFC and so on.
Journal
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- プラズマ・核融合学会誌 = Journal of plasma and fusion research / プラズマ・核融合学会編集委員会 編
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プラズマ・核融合学会誌 = Journal of plasma and fusion research / プラズマ・核融合学会編集委員会 編 72 (10), 1015-1021, 1996-10
プラズマ・核融合学会
