Thermal desorption spectrometry of beryllium plasma facing tiles exposed in the JET tokamak

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9 Scopus citations

Abstract

The phenomena of retention and de-trapping of deuterium (D) and tritium (T) in plasma facing components (PFC) and supporting structures must be understood in order to limit or control total T inventory in larger future fusion devices such as ITER, DEMO and commercial machines. The goal of this paper is to present details of the thermal desorption spectrometry (TDS) system applied in total fuel retention assessment of PFC at the Joint European Torus (JET). Examples of TDS results from beryllium (Be) wall tile samples exposed to JET plasma in PFC configuration mirroring the planned ITER PFC is shown for the first time. The method for quantifying D by comparison of results from a sample of known D content was confirmed acceptable. The D inventory calculations obtained from Ion Beam Analysis (IBA) and TDS agree well within an error associated with the extrapolation from very few data points to a large surface area.

Original languageEnglish
Pages (from-to)135-141
Number of pages7
JournalFusion Engineering and Design
Volume133
DOIs
StatePublished - Aug 2018

Keywords

  • Beryllium
  • Fuel retention
  • JET
  • Plasma facing component
  • Thermal desorption spectrometry
  • Tritium

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