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FP7

Tritium inventory in ITER plasma-facing materials and tritium removal procedures

Funded under: FP7-EURATOM

Abstract

Interactions between the plasma and the vessel walls constitute a major engineering problem for next step fusion devices, such as ITER, determining the choice of the plasma-facing materials. A prominent issue in this choice is the tritium inventory build-up in the vessel, which must be limited for safety reasons. The initial material selection, i.e. beryllium (Be) on the main vessel walls, tungsten (W) on the divertor upper baffle and dome, and carbon fibre composite around the strike points on the divertor plates, results both from the attempt to reduce the tritium inventory and to optimize the lifetime of the plasma-facing components.
In the framework of the EU Task Force on Plasma-Wall Interaction (PWI TF), the many physics aspects governing the tritium inventory are brought together. Together with supporting information from international experts represented by the ITPA SOL/DIV section, this paper describes the present status of knowledge of the in-vessel tritium inventory build-up. Firstly, the main results from present fusion devices in this field are briefly reviewed. Then, the processes involved are discussed: implantation, trapping and diffusion in plasma-facing materials are considered as well as surface erosion and co-deposition of tritium with eroded material. The intermixing of the different materials and its influence on hydrogen retention and co-deposition is a major source of uncertainty on present estimates and is also addressed.

Additional information

Authors: ROTH J, Max-Planck-Institut für Plasmaphysik, EURATOM Association, Teilinstitut Greifswald, Greifswald (DE);SCHMID K, Max-Planck-Institut für Plasmaphysik, EURATOM Association, Teilinstitut Greifswald, Greifswald (DE);OGORODNIKOVA OV, Max-Planck-Institut für Plasmaphysik, EURATOM Association, Teilinstitut Greifswald, Greifswald (DE);TSITRONE E, Département de Recherches sur la Fusion Contrôlée, Association Euratom-CEA sur la Fusion, CEA Cadarache, Saint-Paul-lez-Durance (FR);LOARER T, Département de Recherches sur la Fusion Contrôlée, Association Euratom-CEA sur la Fusion, CEA Cadarache, Saint-Paul-lez-Durance (FR);PHILIPPS V, Institut für Plasmaphysik, Forschungszentrum Jülich, Association EURATOM/FZJ, Trilateral Euregio Cluster, Jülich (DE);BREZINSEK S, Institut für Plasmaphysik, Forschungszentrum Jülich, Association EURATOM/FZJ, Trilateral Euregio Cluster, Jülich (DE);LOARTE A, EFDA Close Support Unit, Garching (DE);COUNSELL GF, EURATOM-UKAEA Fusion Association, Culham Science Centre, Abingdon (GB);DOERNER RP, Fusion Energy Research Program, University of California, La Jolla (US);CAUSEY RA, Sandia National Lababoratory, Livermore (US)
Bibliographic Reference: An article published in: Plasma Physics and Controlled Fusion 50 (2008), 20 pp
Availability: This article can be accessed online by subscribers, and can be ordered online by non-subscribers, at: http://dx.doi.org/10.1088/0741-3335/50/10/103001
Record Number: 200910115 / Last updated on: 2009-01-23
Category: PUBLICATION
Original language: en
Available languages: en
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