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Tritium retention is a crucial point to investigate for next step machines using carbon plasma facing components. In order to access this issue, particle balance has been performed on Tore Supra long discharges, allowing to estimate the wall deuterium inventory. In these conditions, large deuterium detention rates have been observed (up to 50 % of the injected fuel). This paper presents a summary of the experimental results in terms of wall retention during he shot and particle recovery after the shot, as well as after glow discharges and disruptions. Particle balance integrated over a campaign is also estimated and compared with the D inventory deduced from sample analysis. Different mechanisms are then reviewed in order to explain this particle balance, from D particle implantation to carbon porosity filling and codeposition. Rough estimates of each process contribution to the retention rates are given and compared with the experimental observations.

Additional information

Authors: TSITRONE E ET AL, Departement de Recherches sur la Fusion Controlee, Association Euratom-CEA sur la Fusion, CEA Cadarache, Saint-Paul-lez-Durance (FR)
Bibliographic Reference: An oral paper given at: 20th IAEA Fusion Energy Conference Organised by: International Atomic Energy Agency Held at: Centrtro de Fusao Nuclear, Vilamoura (PT)
Availability: Available from Association EURATOM-CEA, Departement de Recherches sur la Fusion Controlee, CEA Cadarache, F-13108 St Paul-Lez-Durance, France Tel: (+33) 4 42 25 70 01; Fax: (+33) 4 42 25 64 21 E-mail:
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