Tritium in plasma-facing components of JET with the ITER-Like-Wall

E. Pajuste (Coresponding Author), A. S. Teimane, G. Kizane, L. Avotina, Mihails Haļitovs, A. Lescinskis, A. Vitins, P. Kalnina, E. Lagzdina, R. J. Zabolockis, JET Contributors

Research output: Contribution to journalArticlepeer-review

3 Citations (Scopus)
8 Downloads (Pure)


The ITER-Like-Wall project has been carried out at the Joint European Torus (JET) to test plasma facing materials relevant to ITER. Materials being tested include both bulk metals (Be andW) and coatings. Tritium accumulation mechanisms and release properties depend both on the wall components, their location in the vacuum vessel, conditions of exposure to plasma and to the material itself. In this study, bulk beryllium limiter tiles, plasma-facing beryllium coated Inconel components from the main chamber, bulk tungsten and tungsten coated carbon fibre composite divertor tiles were analysed. A range of methods have been developed and applied in order to obtain a comprehensive overview on tritium retention and behaviour in different materials of plasma facing components (PFCs). Tritium content and chemical state were studied by the means of chemical or electrochemical dissolution methods and thermal desorption spectroscopy. Tritium distribution in the vacuum vessel and factors affecting its accumulation have been assessed and discussed.

Original languageEnglish
Article number124050
Number of pages10
JournalPhysica Scripta
Issue number12
Publication statusPublished - Dec 2021
Externally publishedYes


  • ITER like wall
  • Joint European torus
  • Plasma facing components
  • Tritium

Field of Science*

  • 1.3 Physical sciences

Publication Type*

  • 1.1. Scientific article indexed in Web of Science and/or Scopus database


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