29th Symposium on Fusion Technology (SOFT 2016)

P1.069 The WEST Plasma Facing Components Protection

5 Sep 2016, 14:20

1h 40m

Foyer 2A (2nd floor), 3A (3rd floor) (Prague Congress Centre)

Board: 69

Poster D. Diagnostics, Data Acquisition and Remote Participation P1 Poster session

Speaker

Jean-Marcel Travere (CEA/IRFM)

Description

The WEST (W Environment for Steady-state Tokamak) [1] project consists in a major upgrade of the superconducting medium size tokamak Tore Supra to minimize risks for the ITER divertor procurement in terms of cost, delays and performance. This modification consists in changing the present circular magnetic configuration to a divertor configuration and implementing an ITER like actively cooled Tungsten divertor. Heat load on divertor target will range from a few MW/m²2 up to 20MW/m²2 depending on the X point location and the heat flux decay length. To operate this new W actively-cooled facility the Wall Monitoring System (WMS) has been set-up to deal with such issues. The WMS will be based on an intensive use of image and multi-sensor analysis. The WMS has been divided in three parts; before discharge a pre-pulse analysis tool to check compatibility between plasma scenario and PFCs operational limits; during discharge a real-time system taking into account all necessary measurements involved in the PFCs protection; after discharge a set of analysis tools accessing WEST database for plasma wall interaction understanding and comparison between prediction and experimental results This paper provides a complete description of the WMS architecture with prelimary results for the three WMS parts: the pre-pulse Power Load Analysis Tool (PLATo) applied to foreseen WEST plasma scenarii on both inertial and actively-cooled components; DWMS real-time system architecture, features and performances and post-pulse analysis software package ThermaVIP capabilities.  1. J. Bucalossi et al., Fusion Engineering and Design 89 (2014) 907–912