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Application of tungsten coated carbon materials for divertor

Research Project

Project/Area Number 14580527
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  Kyushu University, Research Institute for Applied Mechanics, Associate Professor, 応用力学研究所, 助教授 (40227583)

Project Period (FY) 2002 – 2004
Project Status Completed (Fiscal Year 2004)
Budget Amount *help
¥3,400,000 (Direct Cost: ¥3,400,000)
Fiscal Year 2004: ¥700,000 (Direct Cost: ¥700,000)
Fiscal Year 2003: ¥800,000 (Direct Cost: ¥800,000)
Fiscal Year 2002: ¥1,900,000 (Direct Cost: ¥1,900,000)
KeywordsPlasma-wall inyeraction / Tungsten / Carbon / High heat load / Hydrogen isotope / Helium / Divertor plate / Plasma facing materials / プラズマ対向材料
Research Abstract

Tungsten coated isotropic fine grained graphite and CFC have been investigated to examine interface of tungsten and carbon material, surface modification due to plasma exposure and thermal behavior of mock-ups with a cooling tube. Topics are as follows.
(a)Mechanism of carbon diffusion barrier in interface of tungsten and carbon materials.
(b)Surface modification of tungsten due to the irradiation of low energy and high flux hydrogen isotope and helium.
(c)Evaluation of thermal behavior of tungsten coated mock-ups including heat transfer to coolant by high heat load tests and FEM analyses.
Thermal behavior of micro-structure of the interface has been investigated as a function of temperature and time. These results indicate that the diffusion barrier for carbon is not expected to suppress the carbide formation at the joint interface of the tungsten coating above 1600℃. Optimization of structure and thickness will improve the performance. Surface modification and deuterium retention have been examined after the irradiation by low energy and high flux deuterium(100 eV,1×10^<22>D^+m^<-2> s^<-1>,1×10^<26>D^+m^<-2>) using a plasma simulator. Formation of blister depends on kind of tungsten, structure and irradiation temperature. These experimental results indicate that the manufacturing process of tungsten is one of the key factors for the blister formation and the retention of hydrogen isotope on tungsten. Tungsten coated CX-2002U and IG-430U have been brazed on the OFHC with a cooling tube by using Ti foil as braze material. Thermal response and thermal fatigue tests on the mock-ups have been carried out under active cooling conditions using an electron beam. In the case of W/CX-2002U/OFHC, it is demonstrated that the mock-up successfully withstood of heat load at 10 MW/m^2 at steady state. Comparison with the FEM calculation results makes clear quantitatively the thermal behavior of the mock-ups.

Report

(4 results)
  • 2004 Annual Research Report   Final Research Report Summary
  • 2003 Annual Research Report
  • 2002 Annual Research Report
  • Research Products

    (12 results)

All 2005 2004 2003 Other

All Journal Article (9 results) Publications (3 results)

  • [Journal Article] Blister formation and deuterium retention on tungsten exposed to low energy and high flux deuterium plasma2005

    • Author(s)
      K.Tokunaga et al.
    • Journal Title

      Journal of Nuclear Materials 337-339

      Pages: 887-891

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      2004 Annual Research Report 2004 Final Research Report Summary
  • [Journal Article] High heat flux properties of pure tungsten and plasma sprayed tungsten coatings2004

    • Author(s)
      X.Liu et al.
    • Journal Title

      Journal of Nuclear Materials 329-333

      Pages: 687-691

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      2004 Annual Research Report 2004 Final Research Report Summary
  • [Journal Article] High-temperature properties of joint interface of VPS-tungsten coated CFC2004

    • Author(s)
      S.Tamura et al.
    • Journal Title

      Journal of Nuclear Materials 329-333

      Pages: 711-716

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      2004 Annual Research Report 2004 Final Research Report Summary
  • [Journal Article] Thermal response of plasma sprayed tungsten coating to high heat flux2004

    • Author(s)
      X.Liu et al.
    • Journal Title

      Fusion Engineering and Design 70

      Pages: 341-349

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      2004 Annual Research Report 2004 Final Research Report Summary
  • [Journal Article] Thermal response of plasma sprayed tungsten coating to high heat flux2004

    • Author(s)
      X.Liu et al.
    • Journal Title

      Journal of Nuclear Materials 70

      Pages: 341-349

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      2004 Final Research Report Summary
  • [Journal Article] Blister fornation and deuterium retention on tungsten exposed to low energy and high flux deuterium olasma2004

    • Author(s)
      K.Tokunaga, et al.
    • Journal Title

      Journal of Nuclear Materials 337-339

      Pages: 887-891

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      2004 Final Research Report Summary
  • [Journal Article] Surface morphology and helium retention on tungsten exposed to low energy and high flux helium plasma2003

    • Author(s)
      K.Tokunaga, et al.
    • Journal Title

      Journal of Nuclear Materials 313-316

      Pages: 92-96

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      2004 Final Research Report Summary
  • [Journal Article] Erosion and modifications of tungsten-coated carbon and copper under high heat flux2003

    • Author(s)
      L.Xiang et al.
    • Journal Title

      Plasma Science & Technology Vol.5, No.4

      Pages: 1887-1894

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      2004 Annual Research Report 2004 Final Research Report Summary
  • [Journal Article] Erosion and modifications of tungsten-caoted carbon and copper under high heat flux2003

    • Author(s)
      L.Xiang, et al.
    • Journal Title

      Plasma Science & Technology Vol.5, No.4

      Pages: 1887-1894

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      2004 Final Research Report Summary
  • [Publications] K.Tokunaga, et al.: "Surface morphology and helium retention on tungsten exposed to low energy and high flux helium plasma"Journal of Nuclear Materials. 313-316. 92-96 (2003)

    • Related Report
      2003 Annual Research Report
  • [Publications] K.Tokunaga, et al.: "Modification of tungsten coated carbon by low energy and high flux deuterium irradiation"Journal Nuclear Materials. 307-311. 126-129 (2002)

    • Related Report
      2002 Annual Research Report
  • [Publications] K.Tokunaga, et al.: "Effects of helium irradiation on high heat load properties of tungsten"Journal Nuclear Materials. 307-311. 130-134 (2002)

    • Related Report
      2002 Annual Research Report

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Published: 2002-04-01   Modified: 2016-04-21  

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