Search

Experimentally, it has been observed in high-confinement (H-Mode) plasmas with Edge Localised Modes (ELMs) on JET that the pressure pedestal (pe,ped) is degraded by approximately a factor of two when there is a change in electron separatrix density, ne,sep, from 1−4×1019m−3. Previous work using the pedestal stability code EUROPED, has been able to predict the degradation of pe,ped but only for ne,sep≤1.5×1019m−3. In this work, we apply a coupled code JETTO-MISHKA-FRANTIC, to self-consistently predict the transport in the pedestal region and neutral source with varying separatrix conditions. The code feeds back on the transport in the pedestal region to achieve profiles that are marginally stable to ideal MHD modes (continuous ELM model in JETTO).When accounting for the change in electron separatrix temperature (Te,sep), ion separatrix temperature (Ti,sep) and the poloidally integrated neutral flux crossing the separatrix (Γsep,neut) as it changes with ne,sep (according to a scan in ne,sep in the edge code EDGE2D-EIRENE), no degradation in pe,ped was observed in JETTO-MISHKA-FRANTIC in contrast to experiment. Instead, an increase in pe,ped with ne,sep was observed which is driven by an increasing density pedestal (ne,ped). Within the presented JETTO-MISHKA-FRANTIC simulations, changing the pedestal width by a factor of two and a half in normalised poloidal flux (ψn) resulted in an approximately 40% degradation in pe,ped for ne,sep=1−3×1019m−3. This change in pedestal width was not supported by experimental data. A scan in the ratio of particle and energy transport in the pedestal (D/χ) was found to have a negligible effect on pe,ped. Qualitative agreement between JETTO-MISHKA-FRANTIC with EUROPED was found when the input density profiles are identical.

Simulations of JET ITER-like wall high-confinement mode plasmas, including type-I edge-localised modes (ELMs), using JINTRAC for the background plasmas and ERO2.0 for tungsten erosion and transport, predict virtually perfect screening of the primary W erosion sources at the divertor targets during both the ELM and inter-ELM phases. The largest source of W influx to the main plasma is predicted to be the outer vertical divertor due to sputtering by energetic fuel (D, T) atoms from charge-exchange reactions. ERO2.0 predictions accurately reproduce the measured W I emission in the low-field side divertor, but underpredict the W II emission by a factor of 10. Potential reasons for the W II discrepancy include uncertainties in the atomic data, assumptions on the sheath properties and the sputtering angle distribution, and the impact of metastable states.