Fuel retention and carbon deposition on beryllium marker tiles from JET tokamak main chamber limiters investigated by ion beam analysisShow others and affiliations
2022 (English)In: Nuclear Fusion, ISSN 0029-5515, E-ISSN 1741-4326, Vol. 62, no 12, article id 126070Article in journal (Refereed) Published
Abstract [en]
The JET tokamak with the ITER-like wall is operated with arrays of castellated beryllium (Be) limiters in the main chamber. In several locations Be marker tiles were installed for erosion-deposition studies. The castellation sides and the plasma-facing surfaces (PFSs) of Be marker tiles from three different locations of the JET main chamber, from the experimental campaigns 2011-12 (ILW-1) and 2013-14 (ILW-2), were analysed, employing H-2 and He-3 micro-beams in order to determine carbon
Place, publisher, year, edition, pages
IOP Publishing , 2022. Vol. 62, no 12, article id 126070
Keywords [en]
JET tokamak, beryllium, deuterium retention, ion beam analysis, carbon deposition
National Category
Fusion, Plasma and Space Physics
Identifiers
URN: urn:nbn:se:kth:diva-322199DOI: 10.1088/1741-4326/ac9cf0ISI: 000885592700001Scopus ID: 2-s2.0-85142359318OAI: oai:DiVA.org:kth-322199DiVA, id: diva2:1716177
Note
QC 20221205
2022-12-052022-12-052022-12-05Bibliographically approved