Tritium retention in plasma facing materials of JET ITER-Like-Wall retrieved from the vacuum vessel in 2012 (ILW1), 2014 (ILW2) and 2016 (ILW3)

Nuclear Materials and Energy

L. Avotina¹  G. Kizane²  E. Pajuste³  A. Vitins³  A.S. Teimane³ 

[1] Corresponding author at: Institute of Chemical Physics, University of Latvia, 1 Jelgavas Street, Riga, Latvia.;Faculty of Chemistry, University of Latvia, 1 Jelgavas Street, Riga, Latvia;Institute of Chemical Physics, University of Latvia, 1 Jelgavas Street, Riga, Latvia;

关键词: Tritium;    Beryllium;    ITER-Like Wall;    Joint European Torus;    Fuel retention;   

DOI  :  

来源: DOAJ

【 摘 要 】

ITER-Like-Wall (ILW) project has been carried out at Joint European Torus (JET) to test plasma facing materials relevant to International Thermonuclear Experimental Reactor – ITER [1]. Limiters and an upper dump plate of the vacuum vessel are made of bulk beryllium tiles, whereas for the divertor bulk tungsten and tungsten-coated carbon fibre (CFC) composite tiles are used.During the shutdowns in ILW1 (2012), ILW2 (2014) and ILW3 (2016), selected beryllium tiles were removed from the vacuum vessel. In this study, tiles from three positions were analysed, and analysis results were compared regarding both the tile position in the vacuum vessel and differences in the exploitation conditions during the respective three ILW campaigns: ILW1, ILW2, ILW3. Tritium results have been compared to deuterium data published by other authors [2,3].Tritium measurements were performed by two methods - thermal desorption spectroscopy and beryllium chemical etching. Prior to tritium measurements, scanning electron microscopy was used to study structure of the plasma-facing surfaces.Experimental results revealed that tritium content in beryllium samples over all three campaigns is in range of 1.0·1010 to 9.7·1013 tritium atoms per square centimetre of the plasma-facing surface area (atoms/cm2). Highest tritium content was found in the samples from outer wall of the vacuum vessel - up to 4.0·1013 atoms/cm2 in ILW1, 4.2·1013 atoms/cm2 in ILW2 and 9.7·1013 atoms/cm2 in ILW3. Whereas, the lowest - in the upper part of the vacuum vessel: 5.1·1012, 2.8·1012 and 1.0·1010 atoms/cm2 in ILW1, ILW2 and ILW3, respectively. In contrary to the deuterium, in the outer wall tile higher tritium concentrations were found in the central part of the tiles where plasma induced erosion had occurred according to the SEM analysis data. Difference between tritium content in the central part and side part of tile could reach a magnitude of an order - for example, 9.7·1013 and 6.9·1012 atoms/cm2 in the outer wall tile from the ILW3 campaign. Results obtained within this study give possibility to assess tritium retention mechanism and make estimates of its possible inventory in larger machines such as ITER.

【 授权许可】

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