Community Research and Development Information Service - CORDIS

FP7

Recent analysis of key plasma wall interactions issues for ITER

Funded under: FP7-EURATOM

Abstract

Plasma wall interaction (PWI) is important for the material choice in ITER and for the plasma scenarios compatible with material constraints. In this paper, different aspects of the PWI are assessed in their importance for the initial wall materials choice: CFC for the strike point tiles, W in the divertor and baffle and Be on the first wall. Further material options are addressed for comparison, such as W divertor/Be first wall and all-W or all-C. One main parameter in this evaluation is the particle flux to the main vessel wall. One detailed plasma scenario exists for a Q = 10 ITER discharge [FEDERICI G et al., J. Nucl. Mater. 290-293 (2001) 260] which was taken as the basis of further erosion and tritium retention evaluations. As the assessment of steady state wall fluxes from a scaling of present fusion devices indicates that global wall fluxes may be a factor of 4 ± 3 higher, this margin has been adopted as uncertainty of the scaling. With these wall and divertor fluxes, important PWI processes such as erosion and tritium accumulation have been evaluated: It was found that the steady state erosion is no problem for the lifetime of plasma-facing divertor components. Be wall erosion may pose a problem in case of a concentration of the wall fluxes to small wall areas. ELM erosion may drastically limit the PFC lifetime if ELMs are not mitigated to energies below 0.5 MJ. Dust generation is still a process which requires more attention. Conversion from gross or net erosion to dust and the assessment of dust on hot surfaces need to be investigated. For low-Z materials the build-up of the tritium inventory is dominated by co-deposition with eroded wall atoms. For W, where erosion and tritium co-deposition are small, the implantation, diffusion and bulk trapping constitute the dominant retention processes. First extrapolations with models based on laboratory data show small contributions to the inventory.

Additional information

Authors: ROTH J, Max-Planck-Institut für Plasmaphysik, IPP-EURATOM Association, Garching (DE);NEU R, Max-Planck-Institut für Plasmaphysik, IPP-EURATOM Association, Garching (DE);SCHMID K, Max-Planck-Institut für Plasmaphysik, IPP-EURATOM Association, Garching (DE);KRIEGER K, Max-Planck-Institut für Plasmaphysik, IPP-EURATOM Association, Garching (DE);KALLENBACH A, Max-Planck-Institut für Plasmaphysik, IPP-EURATOM Association, Garching (DE);OGORODNIKOVA O, Max-Planck-Institut für Plasmaphysik, IPP-EURATOM Association, Garching (DE);TSITRONE E, Département de Recherches sur la Fusion Contrôlée, Association Euratom-CEA sur la Fusion, CEA Cadarache, Saint-Paul-lez-Durance (FR);LOARER TH, Département de Recherches sur la Fusion Contrôlée, Association Euratom-CEA sur la Fusion, CEA Cadarache, Saint-Paul-lez-Durance (FR);GRISOLIA CH, 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);BERZINSEK S, Institut für Plasmaphysik, Forschungszentrum Jülich, Association EURATOM/FZJ, Trilateral Euregio Cluster, Jülich (DE);LEHNEN M, Institut für Plasmaphysik, Forschungszentrum Jülich, Association EURATOM/FZJ, Trilateral Euregio Cluster, Jülich (DE);LOARTE A, ITER Organization, Fusion Science and Technology Department, St. Paul-lez-Durance (FR);KUKUSHKIN A, ITER Organization, Fusion Science and Technology Department, St. Paul-lez-Durance (FR);COAD P, EURATOM-UKAEA Fusion Association, Culham Science Centre, Abingdon (GB);DOERNER R, University of California-San Diego, La Jolla (US);CAUSEY R, Sandia National Lababoratory, Livermore (US);COUNSELL G, Fusion for Energy, Barcelona (ES);FEDERICI G, Fusion for Energy, Barcelona (ES);ALIMOV V, Japan Atomic Energy Agency, Ibaraki (JP);SHU W, Japan Atomic Energy Agency, Ibaraki (JP);LIPSCHULTZ B, Massachusetts Institute of TechnologyCambridge (US)
Bibliographic Reference: An oral paper given at: 18th International Conference on Plasma-Surface Interactions in Controlled Fusion Device Organised by: Laboratorio Nacional de Fusión Held in: Toledo (ES)
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.jnucmat.2009.01.037
Follow us on: RSS Facebook Twitter YouTube Managed by the EU Publications Office Top