Beryllium accumulation at the inner divertor of JET
2005 (English)In: Journal of Nuclear Materials, ISSN 0022-3115, E-ISSN 1873-4820, Vol. 337-39, no 03-jan, 60-64 p.Article in journal (Refereed) Published
MkIIGB divertor tiles exposed in JET for the 1998-2001 and 1999-2001 campaigns have been used to assess the amount of beryllium and carbon deposited at the inner divertor wall. Total amount of Be at the inner divertor tiles was determined and integrated toroidally. Results were compared with data obtained with optical spectroscopy and good agreement was obtained. The amount of deposited C was computed from the amount of deposited Be assuming that the Be/C ratio arriving in the divertor is the same as the Be/C ratio in the main chamber. On the basis of this analysis we would expect there to be similar to 0.4 kg of C deposited. This gives an average C deposition rate lower than during the MkIIA phase.
Place, publisher, year, edition, pages
2005. Vol. 337-39, no 03-jan, 60-64 p.
divertor, beryllium, carbon based materials, surface analysis, tritium depth profiles, erosion/deposition
IdentifiersURN: urn:nbn:se:kth:diva-14617DOI: 10.1016/j.jnucmat.2004.10.151ISI: 000227789500012ScopusID: 2-s2.0-13844311670OAI: oai:DiVA.org:kth-14617DiVA: diva2:332658
QC 20100525 QC 20111012. 16th International Conference on Plasma Surface Interactions in Controlled Fusion Devices. Portland, ME. MAY 24-28, 2004 2010-08-052010-08-052011-10-12Bibliographically approved