Tritium distributions on W-coated divertor tiles used in the third JET ITER-like wall campaign
- Univ. of Toyama, Gofuku (Japan)
- VTT Technical Research Centre of Finland, Espoo (Finland)
- National Inst. for Fusion Science (NIFS), Toki (Japan)
- National Inst. for Quantum and Radiological Science and Technology, Rokkasho (Japan)
- Univ. of Helsinki (Finland)
- Culham Science Centre, Abingdon (United Kingdom). Culham Centre for Fusion Energy (CCFE)
Tritium (T) distributions on tungsten (W)-coated plasma-facing tiles used in the third ITER-like wall campaign (2015–2016) of the Joint European Torus (JET) were examined by means of an imaging plate technique and β-ray induced x-ray spectrometry, and they were compared with the distributions after the second (2013–2014) campaign. Strong enrichment of T in beryllium (Be) deposition layers was observed after the second campaign. In contrast, T distributions after the third campaign was more uniform though Be deposition layers were visually recognized. The one of the possible explanations is enhanced desorption of T from Be deposition layers due to higher tile temperatures caused by higher energy input in the third campaign.
- Research Organization:
- Culham Science Centre, Abingdon (United Kingdom); Univ. of Helsinki (Finland); Univ. of Toyama, Gofuku (Japan); National Inst. for Fusion Science (NIFS), Toki (Japan)
- Sponsoring Organization:
- European Commission (EC); Japan Society for the Promotion of Science (JSPS)
- Grant/Contract Number:
- 633053; JP26289353
- OSTI ID:
- 1502353
- Journal Information:
- Nuclear Materials and Energy, Vol. 18; ISSN 2352-1791
- Publisher:
- ElsevierCopyright Statement
- Country of Publication:
- United States
- Language:
- English
Web of Science
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