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Self-Passivating Tungsten Based Alloys Obtained by HIP for Application in Fusion Reactors Beyond ITER (DEMO)

  • : Lopez-Ruiz, P1
  • : 1CEIT & Tecnun/University of Navarra
  • : PDF Download
  • : 2012

Abstract

Tungsten is presently the main candidate material for the first wall armour of future fusion reactors. However, the use of tungsten implies an important safety concern in case of a loss-of-coolant accident with air ingress into the reactor vessel. In such a situation, the high temperatures achieved in the in-vessel components would lead to the formation of volatile radioactively tungsten oxides. A possible solution to this important safety issue is the addition to tungsten of oxide forming alloying elements so that at high temperatures in presence of oxygen a self-passivating layer is formed on the surface. In this work, the processing route and properties of W-Cr-Si and W-Cr-Ti alloys manufactured by mechanical alloying and HIP are showed. After HIP, fully dense samples with extremely fine microstructure are obtained. The thermal conductivity and mechanical properties of the samples are measured as a function of temperature. Results of oxidation tests are shown.
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