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FP7

Treatment of ITER plasma facing components: Current status and remaining open issues before ITER implementation

Funded under: FP7-EURATOM

Abstract

The in-vessel tritium inventory control is one of the most ITER challenging issues which has to be resolved to fulfil safety requirements. This is due mainly to the presence of carbon as a constituent of plasma facing components (PFCs) which leads to a high fuel permanent retention. For several years now, physics studies and technological developments have been undertaken worldwide in order to develop reliable techniques which could be used in ITER severe environment (magnetic field, vacuum, high temperature) for in situ tritium recovery. The scope of this contribution is to review the present status of these achievements and define the remaining work to be done in order to propose a dedicated work program.
Different treatment techniques (chemical treatments, photonic cleaning) will be reviewed. In the frame of ITER, they will be compared in terms of fuel removal rate as well as surface accessibility, type of production (gas or particulates), ability to clean mixed material.
And lastly, consequences of bulk trapping observed in tokamak on the techniques currently under development will be addressed.

Additional information

Authors: GRISOLIA C, Département de Recherches sur la Fusion Contrôlée, Association Euratom-CEA sur la Fusion, CEA Cadarache, Saint-Paul-lez-Durance (FR);TSITRONE E, Département de Recherches sur la Fusion Contrôlée, Association Euratom-CEA sur la Fusion, CEA Cadarache, Saint-Paul-lez-Durance (FR);COUNSELL G, EURATOM-UKAEA Fusion Association, Culham Science Centre, Abingdon (GB);COAD P, EURATOM-UKAEA Fusion Association, Culham Science Centre, Abingdon (GB);WIDDOWSON A, EURATOM-UKAEA Fusion Association, Culham Science Centre, Abingdon (GB);DINESCU G, Association Euratom/MdEC, NILPRP, Magurele-Bucharest (RO);SEMEROK A, CEA Saclay, DEN/DPC/SCP/LILM, Bat., Gif sur Yvette (FR);BEKRIS N, Forschungszentrum Karlsruhe, Karlsruhe (DE);HOPF C, Max-Planck-Institut für Plasmaphysik, IPP-EURATOM Association, Garching (DE);ROTH J, Max-Planck-Institut für Plasmaphysik, IPP-EURATOM Association, Garching (DE);RUBEL M, Alfvén Laboratory, Royal Institute of Technology, Association EURATOM-VR, Stockholm (SE)
Bibliographic Reference: An article published in: Fusion Engineering and Design, Article in Press, Corrected Proof (2007)
Availability: This article can be accessed online by subscribers, and can be ordered online by non-subscribers, at: http://dx.doi.org/doi:10.1016/j.fusengdes.2007.05.047
Record Number: 200719350 / Last updated on: 2007-09-06
Category: PUBLICATION
Original language: en
Available languages: en