Internal transport barrier in tokamak and helical plasmas
K Ida, T Fujita - Plasma Physics and Controlled Fusion, 2018 - iopscience.iop.org
The differences and similarities between the internal transport barriers (ITBs) of tokamak and
helical plasmas are reviewed. By comparing the characteristics of the ITBs in tokamak and …
helical plasmas are reviewed. By comparing the characteristics of the ITBs in tokamak and …
Controlling sawtooth oscillations in tokamak plasmas
IT Chapman - Plasma Physics and Controlled Fusion, 2010 - iopscience.iop.org
The sawtooth instability in tokamak plasmas results in a periodic reorganization of the core
plasma. A typical sawtooth cycle consists of a quiescent period, during which the plasma …
plasma. A typical sawtooth cycle consists of a quiescent period, during which the plasma …
Power and particle control
A Loarte, B Lipschultz, AS Kukushkin… - Nuclear …, 2007 - iopscience.iop.org
Progress, since the ITER Physics Basis publication (ITER Physics Basis Editors et al 1999
Nucl. Fusion 39 2137–2664), in understanding the processes that will determine the …
Nucl. Fusion 39 2137–2664), in understanding the processes that will determine the …
Heating and current drive by electron cyclotron waves
R Prater - Physics of plasmas, 2004 - pubs.aip.org
The physics model of electron cyclotron heating (ECH) and current drive (ECCD) is
becoming well validated through systematic comparisons of theory and experiment. This …
becoming well validated through systematic comparisons of theory and experiment. This …
Theoretical description of heavy impurity transport and its application to the modelling of tungsten in JET and ASDEX upgrade
The effects of poloidal asymmetries and heated minority species are shown to be necessary
to accurately describe heavy impurity transport in present experiments in JET and ASDEX …
to accurately describe heavy impurity transport in present experiments in JET and ASDEX …
Tungsten as first wall material in fusion devices
M Kaufmann, R Neu - Fusion Engineering and Design, 2007 - Elsevier
The observation in JET of co-deposition of tritium with carbon has led to a broad discussion
on the replacement of graphite by a high-Z material for the first wall coverage. Moreover, due …
on the replacement of graphite by a high-Z material for the first wall coverage. Moreover, due …
Overview on plasma operation with a full tungsten wall in ASDEX Upgrade
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 …
Upgrade. The conditioning of the device is strongly simplified and short glow discharges are …
Plasma wall interaction and its implication in an all tungsten divertor tokamak
ASDEX Upgrade has recently finished its transition towards an all-W divertor tokamak, by
the exchange of the last remaining graphite tiles to W-coated ones. The plasma start-up was …
the exchange of the last remaining graphite tiles to W-coated ones. The plasma start-up was …
Analysis and expansion of the quasi-continuous exhaust (QCE) regime in ASDEX Upgrade
The quasi-continuous exhaust (QCE) regime, formerly known as either type-II ELM or small
ELM regime is studied in ASDEX Upgrade. The regime is a natural type-I ELM-free H-mode …
ELM regime is studied in ASDEX Upgrade. The regime is a natural type-I ELM-free H-mode …
Tokamak operation with high-Z plasma facing components
A Kallenbach, R Neu, R Dux… - Plasma physics and …, 2005 - iopscience.iop.org
Plasma operation with high-Z plasma facing components is investigated with regard to
sputtering, core impurity contamination and scenario restrictions. A simple model based on …
sputtering, core impurity contamination and scenario restrictions. A simple model based on …