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Abstract

The feasibility assessment and design qualification of the plasma facing components for tokamaks such as NET and ITER incorporated a test programme on industrially fabricated components. A high power electron beam test facility, designed to provide the maximum performance and flexibility to implement and interpret plasma facing component mock-up experiments, was built with thermomechanical and thermohydraulic behaviour of high heat fluxes in mind. Tests were performed to verify the capability of the power supply, the gun power profiles and the thermomechanical measurements and data acquisition system on relevant mock-ups. A synthesis of the first results obtained with relevant ITER divertor mock-ups is presented.

Additional information

Authors: MAYAUX G ET AL., CEA, Département de Recherches sur la Fusion Contrôlée, CEN Cadarache, Saint-Paul-lez-Durance (FR);CARDELLA A, NET Team, Garching (DE);FEBVRE M, Framatome, Le Creusot (FR)
Bibliographic Reference: Paper presented: 17th Symposium on Fusion Technology, Roma (IT), September 14-18, 1992
Availability: Available from (1) as Paper EN 37062 ORA
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