We investigated hydrogen retention in Tore-Supra tokamak tiles after several plasma campaigns (tiles #14 and #20 from the inboard bumper, 1995–1999). It was found that most hydrogen is retained in deposited and top surface layers; moreover, hydrogen diffuses into the graphite bulk.
Materials analysis
Hydrogen Retention in Tore-Supra Tiles
Study of hydrogen retention in Tore-Supra tokamak tiles.
Irradiation summary
| Quantity | Value |
|---|---|
| Ion flux density $j$ | $(1\text{–}2)\times10^{19}\ \mathrm{at\,s^{-1}\,m^{-2}}$ |
| Ion energy $E_i$ | $\sim 100\ \mathrm{eV}$ |
| Tile temperature | $500\text{–}600\ \mathrm{K}$ |
| ### He glow conditioning | |
| $> 20$ discharges; He$^{+}$ bombardment of inner wall. |
| Quantity | Value |
|---|---|
| He$^{+}$ energy | $\sim 200\ \mathrm{eV}$ |
| He$^{+}$ flux density | $6\times10^{17}\ \mathrm{at\,s^{-1}\,m^{-2}}$ |
Gallery
