TY - JOUR
T1 - Modelling of the material transport and layer formation in the divertor of JET
T2 - Comparison of ITER-like wall with full carbon wall conditions
AU - Kirschner, A.
AU - Matveev, D.
AU - Borodin, D.
AU - Airila, Markus
AU - Brezinsek, S.
AU - Groth, M.
AU - Wiesen, S.
AU - Widdowson, A.
AU - Beal, J.
AU - Esser, H. G.
AU - Likonen, Jari
AU - Bekris, N.
AU - Ding, R.
AU - JET-EFDA contributors
PY - 2015/7/22
Y1 - 2015/7/22
N2 - 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.
AB - 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.
UR - http://www.scopus.com/inward/record.url?scp=84937683158&partnerID=8YFLogxK
U2 - 10.1016/j.jnucmat.2014.10.072
DO - 10.1016/j.jnucmat.2014.10.072
M3 - Article
AN - SCOPUS:84937683158
SN - 0022-3115
VL - 463
SP - 116
EP - 122
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
M1 - 48569
ER -