Abstract
A dedicated study on fuel retention has been launched in Tore Supra, which includes a D wall-loading campaign and the dismantling of the main limiter (Deuterium Inventory in Tore Supra, DITS project). This paper presents new results from a second post-mortem analysis campaign on 40 tiles with special emphasis on the D retention in the gaps. SIMS analysis reveals that only 1/3 of the thickness of deposits in the plasma shadowed zones are due to the DITS wall-loading campaign. As pre-DITS deposits contain less D than DITS deposits, the contribution of DITS to the D inventory is about 30–50%. The new estimate for the total amount of D retained in the Tore Supra limiter is 1.7 × 1024 atoms, close to the previous estimate, with the gap surfaces contributing about 33%. NRA measurements show a stepped decrease of D along the gap with strong asymmetries between different gap orientations.
Original language | English |
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Pages (from-to) | S757-S760 |
Number of pages | 4 |
Journal | Journal of Nuclear Materials |
Volume | 415 |
Issue number | 1 |
DOIs | |
Publication status | Published - 2011 |
MoE publication type | A1 Journal article-refereed |
Event | 19th International Conference on Plasma Surface Interactions in Controlled Fusion Devices, PSI-19 - San Diego, United States Duration: 24 May 2010 → 28 May 2010 |