Impurity seeding for tokamak power exhaust: from present devices via ITER to DEMO

A Kallenbach, M Bernert, R Dux, L Casali… - Plasma Physics and …, 2013 - iopscience.iop.org
A future fusion reactor is expected to have all-metal plasma facing materials (PFMs) to
ensure low erosion rates, low tritium retention and stability against high neutron fluences. As …

Theoretical and experimental aspects of non-equilibrium plasmas in different regimes: fundamentals and selected applications

G Colonna, CD Pintassilgo, F Pegoraro… - The European Physical …, 2021 - Springer
This paper presents recent activities covering different plasma fields, from both theoretical
and experimental point of views. An overview of the present interests of the scientific …

On the physics guidelines for a tokamak DEMO

H Zohm, C Angioni, E Fable, G Federici… - Nuclear …, 2013 - iopscience.iop.org
The physics base for the ITER Physics Design Guidelines is reviewed in view of application
to DEMO and areas are pointed out in which improvement is needed to arrive at a consistent …

[HTML][HTML] Plasma-surface interaction in the Be/W environment: conclusions drawn from the JET-ILW for ITER

S Brezinsek, JET-EFDA contributors - Journal of nuclear materials, 2015 - Elsevier
Abstract The JET ITER-Like Wall experiment (JET-ILW) provides an ideal test bed to
investigate plasma-surface interaction (PSI) and plasma operation with the ITER plasma …

An overview of creep in tungsten and its alloys

J Webb, S Gollapudi, I Charit - … Journal of Refractory Metals and Hard …, 2019 - Elsevier
The objective of this short review is to provide an overview on the current understanding of
creep in tungsten and its alloys. Tungsten is a high temperature material on account of its …

DEMO divertor limitations during and in between ELMs

RP Wenninger, M Bernert, T Eich, E Fable… - Nuclear …, 2014 - iopscience.iop.org
Operation of DEMO in comparison to ITER will be significantly more demanding, as various
additional limitations of physical and technical nature have to be respected. In particular a …

Impact of nitrogen seeding on confinement and power load control of a high-triangularity JET ELMy H-mode plasma with a metal wall

C Giroud, GP Maddison, S Jachmich, F Rimini… - Nuclear …, 2013 - iopscience.iop.org
This paper reports the impact on confinement and power load of the high-shape 2.5 MA
ELMy H-mode scenario at JET of a change from all carbon plasma-facing components to an …

Overview on plasma operation with a full tungsten wall in ASDEX Upgrade

R Neu, A Kallenbach, M Balden, V Bobkov… - Journal of Nuclear …, 2013 - Elsevier
Operation with all tungsten plasma facing components has become routine in ASDEX
Upgrade. The conditioning of the device is strongly simplified and short glow discharges are …

Optimized tokamak power exhaust with double radiative feedback in ASDEX Upgrade

A Kallenbach, M Bernert, T Eich, JC Fuchs… - Nuclear …, 2012 - iopscience.iop.org
A double radiative feedback technique has been developed on the ASDEX Upgrade
tokamak for optimization of power exhaust with a standard vertical target divertor. The main …

Overview of ASDEX Upgrade results

A Kallenbach, ASDEX Upgrade Team… - Nuclear …, 2017 - iopscience.iop.org
Abstract The ASDEX Upgrade (AUG) programme is directed towards physics input to critical
elements of the ITER design and the preparation of ITER operation, as well as addressing …