Implementing ITER-like targets as the WEST divertor is the purpose of the project.
The divertor is one of the key components of a tokamak: it is the divertor that receives most of the heat fluxes and particles coming from the central plasma. The associated heat fluxes are high (10-20 MW/m²) and necessitate the development of advanced technologies in order to remove them on a continuous basis.
The divertor fulfils a two-fold function: it extracts the ash produced by the reaction and removes part of the heat generated by the system while limiting plasma contamination by other impurities. The production and operation of the Iter tungsten components emerge truly as a “first” in the world. They create new challenges that the WEST Project will be able to meet.
The WEST divertor elements follow as closely as possible the design and manufacturing processes foreseen for the ITER divertor. The same tungsten tile geometry and bonding to the heat sink are used to build fingers. In addition, the same tile final machining and “shaping” (appropriate studies are on-going in the ITER organization) will be applied. The high heat flux areas of the plasma-facing units (PFU) or fingers are similarly located in a flat section for both designs (WEST PFU length is 1/3 of those which make up the ITER divertor). With ~16 000 monoblock tiles, the WEST divertor represents 14% of the ITER inner vertical divertor target needs, offering the capacity to qualify a manufacturing process at the required industrial scale through a first significant production series.
Last update : 11/26 2013 (3)
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