Modelling of the material transport and layer formation in the divertor of JET: Comparison of ITER-like wall with full carbon wall conditions

A. Kirschner, D. Matveev, D. Borodin, Markus Airila, S. Brezinsek, M. Groth, S. Wiesen, A. Widdowson, J. Beal, H. G. Esser, Jari Likonen, N. Bekris, R. Ding, JET-EFDA contributors

    Research output: Contribution to journalArticleScientificpeer-review

    24 Citations (Scopus)

    Abstract

    Abstract Impurity transport within the inner JET divertor has been modelled with ERO to estimate the transport to and the resulting deposition at remote areas. Various parametric studies involving divertor plasma conditions and strike point position have been performed. In JET-ILW (beryllium main chamber and tungsten divertor) beryllium, flowing from the main chamber into the divertor and then effectively reflected at the tungsten divertor tiles, is transported to remote areas. The tungsten flux to remote areas in L-Mode is in comparison to the beryllium flux negligible due to small sputtering. However, tungsten is sputtered during ELMs in H-Mode conditions. Nevertheless, depending on the plasma conditions, strike point position and the location of the remote area, the maximum resulting tungsten flux to remote areas is at least ∼3 times lower than the corresponding beryllium flux. Modelled beryllium and tungsten deposition on a rotating collector probe located below tile 5 is in good agreement with measurements if the beryllium influx into the inner divertor is assumed to be in the range of 0.1% relative to the deuterium ion flux and erosion due to fast charge exchange neutrals is considered. Comparison between JET-ILW and JET-C is presented.
    Original languageEnglish
    Article number48569
    Pages (from-to)116-122
    JournalJournal of Nuclear Materials
    Volume463
    DOIs
    Publication statusPublished - 22 Jul 2015
    MoE publication typeA1 Journal article-refereed

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