Overview of tritium retention in divertor tiles and dust particles from the JET tokamak with the ITER-like wallShow others and affiliations
2024 (English)In: Nuclear Fusion, ISSN 0029-5515, E-ISSN 1741-4326, Vol. 64, no 1, article id 016032Article in journal (Refereed) Published
Abstract [en]
Divertor tiles after Joint European Torus-ITER like wall (JET-ILW) campaigns and dust collected after JET-C and JET-ILW operation were examined by a set of complementary techniques (full combustion and radiography) to determine the total, specific and areal tritium activities, poloidal tritium distribution in the divertor and the presence of that isotope in individual dust particles. In the divertor tiles, the majority of tritium is detected in the surface region and, the areal activities in the ILW divertor are in the 0.5-12 kBq cm-2 range. The activity in the ILW dust is associated mainly with the presence of carbon particles being a legacy from the JET-C operation. The total tritium activities show significant differences between the JET operation with ILW and the earlier phase with the carbon wall (JET-C) indicating that tritium retention has been significantly decreased in the operation with ILW.
Place, publisher, year, edition, pages
IOP Publishing , 2024. Vol. 64, no 1, article id 016032
Keywords [en]
JET, ITER like wall, tritium, divertor, dust
National Category
Fusion, Plasma and Space Physics
Identifiers
URN: urn:nbn:se:kth:diva-340981DOI: 10.1088/1741-4326/ad0c08ISI: 001113351800001Scopus ID: 2-s2.0-85179883234OAI: oai:DiVA.org:kth-340981DiVA, id: diva2:1820297
Note
QC 20250318
2023-12-182023-12-182025-03-18Bibliographically approved