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Rev Sci Instrum. 2016 Feb;87(2):023506. doi: 10.1063/1.4941717.

Detecting divertor damage during steady state operation of Wendelstein 7-X from thermographic measurements.

The Review of scientific instruments

A Rodatos, H Greuner, M W Jakubowski, J Boscary, G A Wurden, T S Pedersen, R König

Affiliations

  1. Max Planck Institute for Plasma Physics, Wendelsteinstr. 1, Greifswald, Germany.
  2. Max Planck Institute for Plasma Physics, Boltzmannstr. 2, Garching, Germany.
  3. Los Alamos National Laboratory, Los Alamos, New Mexico 87544, USA.

PMID: 26931848 DOI: 10.1063/1.4941717

Abstract

Wendelstein 7-X (W7-X) aims to demonstrate the reactor capability of the stellarator concept, by creating plasmas with pulse lengths of up to 30 min at a heating power of up to 10 MW. The divertor plasma facing components will see convective steady state heat flux densities of up to 10 MW/m(2). These high heat flux target elements are actively cooled and are covered with carbon fibre reinforced carbon (CFC) as plasma facing material. The CFC is bonded to the CuCrZr cooling structure. Over the life time of the experiment this interface may weaken and cracks can occur, greatly reducing the heat conduction between the CFC tile and the cooling structure. Therefore, there is not only the need to monitor the divertor to prevent damage by overheating but also the need to detect these fatigue failures of the interface. A method is presented for an early detection of fatigue failures of the interface layer, solely by using the information delivered by the IR-cameras monitoring the divertor. This was developed and validated through experiments made with high heat flux target elements prior to installation in W7-X.

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