4.5 Article Proceedings Paper

The WEST project: Testing ITER divertor high heat flux component technology in a steady state tokamak environment

期刊

FUSION ENGINEERING AND DESIGN
卷 89, 期 7-8, 页码 907-912

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ELSEVIER SCIENCE SA
DOI: 10.1016/j.fusengdes.2014.01.062

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ITER; WEST; Plasma-facing components; Tungsten; Divertor; Steady state operation

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The WEST project recently launched at Cadarache consists in transforming Tore Supra in an X-point divertor configuration while extending its long pulse capability, in order to test the ITER divertor technology. The implementation of a full tungsten actively cooled divertor with plasma facing unit representative of ITER divertor targets will allow addressing risks both in terms of industrial-scale manufacturing and operation of such components. Relevant plasma scenarios are foreseen for extensive testing under high heat load in the 10-20 MW/m(2) range and ITER-like fluences (1000 s pulses). Plasma facing unit monitoring and development of protection strategies will be key elements of the WEST program. WEST is scheduled to enter into operation in 2016, and will provide a key facility to prepare and be prepared for ITER. (c) 2014 Elsevier B.V. All rights reserved.

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