Journal
FUSION ENGINEERING AND DESIGN
Volume 133, Issue -, Pages 135-141Publisher
ELSEVIER SCIENCE SA
DOI: 10.1016/j.fusengdes.2018.05.075
Keywords
Thermal desorption spectrometry; Beryllium; Plasma facing component; Fuel retention; JET; Tritium
Categories
Funding
- Euratom research and training programme [633053]
- RCUK Energy Programme [EP/P012450/1]
- UK's National Nuclear User Facility
- Henry Royce Institute for Advanced Materials
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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.
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