We report on neutral flux measurements in the full tungsten ASDEX Upgrade from the recently upgraded pressure gauge system in a wide range of plasma parameters and divertor conditions in L-mode plasmas. We compare these measurements with the ion and neutral fluxes in similar older discharges in presence of carbon tar-get plates. We then show the qualitative relationship between the divertor poloidal distribution of the neutral flux density and the inner and outer divertor plasma regimes. During plasma density rise, when the plasma at one particular target de-taches, the local flux increases abruptly producing a strong in-out asymmetry in the neutral flux distribution in the divertor. The neutral flux at the high field side increase linearly...
Numerical simulations of divertor power and particle fluxes in L-mode exhaust scenarios are presente...
A qualitative as well as quantitative simulation of experimentally observed plasma parameters in the...
The key problem for the use of carbon in a future fusion device is the formation of tritium containi...
The scrape-off layer and divertor plasma conditions have been carefully analysed in dedicated ASDEX ...
Divertor detachment is a prerequisite for large burning plasma fusion devices. The understanding of ...
Neutral density profiles have been derived along the outboard di-vertor target of Alcator C-Mod and ...
In situ, two-dimensional (2D) Langmuir probe measurements across a large part of the TCV outer diver...
Recently, much effort has been dedicated to understanding the bifurcation involved in the transition...
| openaire: EC/H2020/633053/EU//EUROfusionPairs of ASDEX Upgrade L-mode discharges with the toroidal...
In this paper, results of two approaches to account for the neutral density are reported, which subs...
Electron pressure proles have been obtained in the outer midplane and along the divertor target usin...
Abstract. Part I presented a detailed analysis of outer divertor plasma conditions in low-density L-...
Part I (Aho-Mantila L. et al 2012 Nucl. Fusion 52 103006) presented a detailed analysis of outer div...
The diagnosis of tokamak divertor plasmas is limited in the ability to understand the behaviour and ...
The understanding of divertor physics and the evolution of divertor detachment is crucial for develo...
Numerical simulations of divertor power and particle fluxes in L-mode exhaust scenarios are presente...
A qualitative as well as quantitative simulation of experimentally observed plasma parameters in the...
The key problem for the use of carbon in a future fusion device is the formation of tritium containi...
The scrape-off layer and divertor plasma conditions have been carefully analysed in dedicated ASDEX ...
Divertor detachment is a prerequisite for large burning plasma fusion devices. The understanding of ...
Neutral density profiles have been derived along the outboard di-vertor target of Alcator C-Mod and ...
In situ, two-dimensional (2D) Langmuir probe measurements across a large part of the TCV outer diver...
Recently, much effort has been dedicated to understanding the bifurcation involved in the transition...
| openaire: EC/H2020/633053/EU//EUROfusionPairs of ASDEX Upgrade L-mode discharges with the toroidal...
In this paper, results of two approaches to account for the neutral density are reported, which subs...
Electron pressure proles have been obtained in the outer midplane and along the divertor target usin...
Abstract. Part I presented a detailed analysis of outer divertor plasma conditions in low-density L-...
Part I (Aho-Mantila L. et al 2012 Nucl. Fusion 52 103006) presented a detailed analysis of outer div...
The diagnosis of tokamak divertor plasmas is limited in the ability to understand the behaviour and ...
The understanding of divertor physics and the evolution of divertor detachment is crucial for develo...
Numerical simulations of divertor power and particle fluxes in L-mode exhaust scenarios are presente...
A qualitative as well as quantitative simulation of experimentally observed plasma parameters in the...
The key problem for the use of carbon in a future fusion device is the formation of tritium containi...