journal article·2011-08

An overview of nuclear micro-beam analysis of surface and bulk fuel retention in carbon-fibre composites from Tore Supra

P. Petersson, G. Possnert, M. Rubel, T. Dittmar, B. Pégourié, E. Tsitrone, E. Wessel

Journal of Nuclear Materials· Volume 415· Issue 1
Publisher page

Abstract

Surface and bulk retention of deuterium in tiles of the pump limiter from Tore Supra was examined with nuclear reaction analysis using both standard and micro-beam techniques. The aim was to determine the variations in the content and distribution of fuel species in carbon-fibre composites. On plasma-facing surfaces from the deposition zone, the D content reaches 2.5 × 10 19 cm −2 in about 8 μm thick top layer, but lateral differences reach even more than one order of magnitude. This is also measured in the erosion zone: 6.6 × 10 17 cm −2 to 7.7 × 10 18 cm −2 D atoms. Bulk content was examined on cross-sections opened by fracturing the tiles. Fuel is detected up to the depth of 1–1.5 mm beneath the plasma-facing surface in tiles from both the erosion and deposition zones. It occurs in bands, about 100 μm wide and several mm long, roughly parallel to the original plasma-facing surface.
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Research context

OpenAlex topics: Fusion materials and technologies · Nuclear Materials and Properties · Diamond and Carbon-based Materials Research

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