• Title of article

    Selection of candidate doped graphite materials as plasma facing components for HT-7U device

  • Author/Authors

    Guo، نويسنده , , Q.G and Li، نويسنده , , J.G and Noda، نويسنده , , N and Kubota، نويسنده , , Y and Chen، نويسنده , , J.L and Liu، نويسنده , , Zh.J and Liu، نويسنده , , L and Song، نويسنده , , J.R، نويسنده ,

  • Issue Information
    روزنامه با شماره پیاپی سال 2003
  • Pages
    5
  • From page
    144
  • To page
    148
  • Abstract
    Selection of candidate materials for plasma facing material (PFM) in HT-7U device and plasma–wall interactions are critically important to reach high plasma performance. Based on concentrated research on multi-element doped graphite containing B, Si and Ti, two kinds of doped graphites have been chosen as candidates for PFM in HT-7U. Doped graphite GBST1308 with the dopant concentration of 1% B, 2.5% Si, 7.5% Ti was developed as low-Z PFM for reducing the chemical sputtering and suppressing the radiation enhanced sublimation, and successfully used as the new limiter material in last two campaigns of HT-7 tokamak experiments. Doped graphite with the composition of 2.5% Si, 7.5% Ti has improved mechanical properties and thermal conductivity of 314 W/m K at room temperature. TDS and high heat flux experiments results demonstrated that such doped graphites are promising candidate plasma facing components for HT-7U.
  • Keywords
    HT-7U , B2-EIRENE code , Doped graphite , TDS , Plasma facing component , High heat flux test
  • Journal title
    Journal of Nuclear Materials
  • Serial Year
    2003
  • Journal title
    Journal of Nuclear Materials
  • Record number

    1356951