Abstract
| Original language | English |
|---|---|
| Pages (from-to) | 419-423 |
| Journal | Journal of Nuclear Materials |
| Volume | 313-316 |
| DOIs | |
| Publication status | Published - 2003 |
| MoE publication type | A1 Journal article-refereed |
| Event | Plasma-Surface Interactions in Controlled Fusion Devices 15 - Gifu, Japan Duration: 26 May 2002 → 31 May 2002 |
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Keywords
- plasma-wall interactions
- divertor
- tritium retention
- rutherford backscattering
- SIMS
- fusion energy
- fusion reactors
- JET
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Erosion/deposition in JET during the period 1999-2001. / Coad, J.P. (Corresponding Author); Andrew, P.; Hole, D.E.; Lehto, S.; Likonen, J.; Matthews, G.F.; Rubel, M.; JET-EFDA collaborators.
In: Journal of Nuclear Materials, Vol. 313-316, 2003, p. 419-423.Research output: Contribution to journal › Article › Scientific › peer-review
TY - JOUR
T1 - Erosion/deposition in JET during the period 1999-2001
AU - Coad, J.P.
AU - Andrew, P.
AU - Hole, D.E.
AU - Lehto, S.
AU - Likonen, J.
AU - Matthews, G.F.
AU - Rubel, M.
AU - JET-EFDA collaborators
PY - 2003
Y1 - 2003
N2 - Coated divertor and wall tiles exposed in JET for the 1999–2001 operations have been used to assess erosion/deposition. Deposited films of up to 90 μm thickness at the inner wall of the divertor tiles are, for the most part, enriched in beryllium and other metals, whilst carbon is probably chemically sputtered from these tiles and transported to shadowed regions of the inner divertor. However, from the composition at the surface of the tiles, it appears that the chemical erosion was ‘switched off’ by reducing the JET vessel wall temperature for the last part of the operations to 200 °C. Thick powdery deposits localised at the ion transport limit at each corner of the divertor may be due to physical sputtering. Erosion of the coatings is seen at the outer divertor wall, and on all the inner wall and outer limiter tiles.
AB - Coated divertor and wall tiles exposed in JET for the 1999–2001 operations have been used to assess erosion/deposition. Deposited films of up to 90 μm thickness at the inner wall of the divertor tiles are, for the most part, enriched in beryllium and other metals, whilst carbon is probably chemically sputtered from these tiles and transported to shadowed regions of the inner divertor. However, from the composition at the surface of the tiles, it appears that the chemical erosion was ‘switched off’ by reducing the JET vessel wall temperature for the last part of the operations to 200 °C. Thick powdery deposits localised at the ion transport limit at each corner of the divertor may be due to physical sputtering. Erosion of the coatings is seen at the outer divertor wall, and on all the inner wall and outer limiter tiles.
KW - plasma-wall interactions
KW - divertor
KW - tritium retention
KW - rutherford backscattering
KW - SIMS
KW - fusion energy
KW - fusion reactors
KW - JET
U2 - 10.1016/S0022-3115(02)01403-4
DO - 10.1016/S0022-3115(02)01403-4
M3 - Article
VL - 313-316
SP - 419
EP - 423
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
SN - 0022-3115
ER -