EDGE MODELLING WITH SOLEDGED2-EIRENE CODE IN RFX-MOD AND TCV FUSION DEVICES

The knowledge of edge plasma transport parameters and plasma edge phenomena is a key element in the design the divertor and the first wall for a magnetically confined fusion experiment.In this report will be presented the modelling performed in two fusion experiments: the RFX-mod(Reversed Field eXperiment) reversed field pinch experiment and the small size TCV (Tokamak à Configuration Variable) tokamak. In RFX-mod heat flux deposition profiles on the wall have been evaluated from infrared temperature measurements of insertable graphite limiters.In TCV device experiments have been performed in Snowflakeand Single Null divertor magnetic configurationsto evaluate the relative advantage in terms of divertor heat load anddetachment threshold.Modelling of edge radial profiles and divertor parameters and heat fluxes has been done using the SOLEDGE2D-EIRENE edge code.In RFX-mod edge modelling has shown that measured decay lengths are compatible with energy diffusion coefficients in Scrape Off Layer (SOL) smaller than those commonly evaluated at plasma edge; the cause of the reduced diffusion in the SOL will be discussed in the paper.In TCV only preliminary results of the single null configuration have been obtained showing that transport parameters have to be increased with the density.