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Thermal response of tungsten-coated carbon divertor mock-ups and effects of particle irradiation on their properties.

Research Project

Project/Area Number 11680500
Research Category

Grant-in-Aid for Scientific Research (C)

Allocation TypeSingle-year Grants
Section一般
Research Field Nuclear fusion studies
Research InstitutionKYUSHU UNIVERSITY

Principal Investigator

TOKUNAGA Kazutoshi  Research Institute for Applied Mechanics, KYUSHU UNIVERSITY Ass.Prof., 応用力学研究所, 助教授 (40227583)

Project Period (FY) 1999 – 2000
Project Status Completed (Fiscal Year 2000)
Budget Amount *help
¥2,100,000 (Direct Cost: ¥2,100,000)
Fiscal Year 2000: ¥900,000 (Direct Cost: ¥900,000)
Fiscal Year 1999: ¥1,200,000 (Direct Cost: ¥1,200,000)
KeywordsPlasma-wall interaction / Tungsten / carbon materials / High heat load / Hydrogen isotope / Helium / High heat flux components / Divertor plate
Research Abstract

CX-2002U and IG-430U coated by vacuum plasma sprayed tungsten (VPS-W) were developed as a light-weight high-Z plasma-facing material. After brazing them on OFHC blocks using a titanium foil and silver based materials, their thermal response and thermal fatigue properties were examined. Heat load resistance of the VPS-W coated CX-2002U/OFHC was much better than that of the VPS-W coated IG-430U/OFHC due to the high thermal conductivity of CX-2002U(350 W/mK). Neither cracks nor exfoliation were observed on the W surface and the braze interface even after 160 cycles of heat load for 20s at 10 MW/m^2 in the case of Ti brazing. The plasma sprayed tungsten coated carbon/carbon fiber composite (VPS-W/CX-2002U) and powder metallurgy tungsten (PM-W) were exposed to a high flux of deuterium/helium particles with a low energy (100 eV). Surface modification and deuterium/helium retention property after the exposure have been investigated to prove the suitability of such materials in fusion devices. Blisters were formed on the PM-W by deuterium irradiation to a fluence of 7.5x10^<25> m^<-2>. On the other hand, no modification was observed for the VPS-W/CX-2002U.This difference may be attributed to surface morphology. Deuterium desorption property from VPS-W/CX-2002U was different from that of the PM-W.Deuterium implanted on the surface of the VPS-W/CX-2002U diffused into and trapped in the CX-2002U.

Report

(3 results)
  • 2000 Annual Research Report   Final Research Report Summary
  • 1999 Annual Research Report
  • Research Products

    (11 results)

All Other

All Publications (11 results)

  • [Publications] K.Tokunaga,T.Matsubara et.al: "Changes of composition and microstructure of joint interface of tungsten coated carbon by high heat flux"Journal of Nuclear Materials. 283-287. 1121-1127 (2000)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      2000 Final Research Report Summary
  • [Publications] K.Tokunaga,N.Yoshida et.al.: "High heat flux test of actively cooled tungsten-coated carbon divertor mock-ups"Fusion Engineering and Design. 49-50. 371-376 (2000)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      2000 Final Research Report Summary
  • [Publications] K.Tokunaga,N.Yoshida et.al.: "Thermal response and Material Degradation of tugsten-coated carbon divertor mock-ups by high heat flux"Journal of Plasma and Fusion Research Series. 3. 260-264 (2000)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      2000 Final Research Report Summary
  • [Publications] K.Tokunaga, N.Yoshida, Y.Kubota, N.Noda, Y.Imamura, T.Oku, A.Kurumada, T.Sogabe, T.Kato, L.Ploechl: "High heat flux test of actively cooled tungsten-coated carbon divertor mock-ups"Fusion Engineering and Design. 49-50. 371-376 (2000)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      2000 Final Research Report Summary
  • [Publications] K.Tokunaga, T.Matsubara, Y.Miyamoto, Y.Takao, N.Yoshida, N.Noda, Y.Kubota, T.Sogabe, T.Kato, L.Ploechl: "Canages of composition and microstructure of joint interface of tungsten coated carbon by high heat flux"Journal of Nuclear Materials. 283-287. 1121-1127 (2000)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      2000 Final Research Report Summary
  • [Publications] K.Tokunaga, N.Yoshida, Y.Kubota, N.Noda, Y.Imamura, A.Kurumada, T.Oku, T.Sogabe, B.T.Suzuki, T.Kato, L.Ploechl: "Thermal Response and Material Degradation of Tungsten-Coated Carbon Divertor Mock-ps by High Heat Flux"Journal of Plasma and Fusion Research SERIES. Volume 3. 260-264 (2000)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      2000 Final Research Report Summary
  • [Publications] K.Tokunaga,T.Matsubara et.al: "Changes of composition and microstructure of joint interface of tungsten coated carbon by high heat flux"Journal of Nuclear Materials. 283-287. 1121-1127 (2000)

    • Related Report
      2000 Annual Research Report
  • [Publications] K.Tokunaga,N.Yoshida et.al.: "High heat flux test of actively cooled tungsten-coated carbon divertor mock-ups"Fusion Engineering and Design. 49-50. 371-376 (2000)

    • Related Report
      2000 Annual Research Report
  • [Publications] K.Tokunaga,N.Yoshida et.al.: "Thermal response and Material Degradation of tugsten-coated carbon divertor mock-ups by high heat flux"Journal of Plasma and Fusion Research Series. 3. 260-264 (2000)

    • Related Report
      2000 Annual Research Report
  • [Publications] K.Tokunaga,N.Yoshida,et al.: "Behavior of plasma-sprayed tungsten coatings on CFC and Graphite under high heat load"Journal of Nuclear Naterials. 266-269. 1224-1229 (1999)

    • Related Report
      1999 Annual Research Report
  • [Publications] 松原監壮、徳永和俊、他: "電子ビーム照射による高熱流束負荷を受けたVPS-W溶射被膜/炭素系基材の界面近傍における組成分析と損傷解析"溶射. 36巻・1号. 28-37 (1999)

    • Related Report
      1999 Annual Research Report

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Published: 1999-04-01   Modified: 2016-04-21  

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