Scaling of the tokamak near the scrape-off layer H-mode power width and implications for ITER

T Eich, AW Leonard, RA Pitts, W Fundamenski… - Nuclear …, 2013 - iopscience.iop.org
A multi-machine database for the H-mode scrape-off layer power fall-off length, λ q in JET,
DIII-D, ASDEX Upgrade, C-Mod, NSTX and MAST has been assembled under the auspices …

Overview of progress in European medium sized tokamaks towards an integrated plasma-edge/wall solution a

H Meyer, T Eich, M Beurskens, S Coda, A Hakola… - Nuclear …, 2017 - iopscience.iop.org
Integrating the plasma core performance with an edge and scrape-off layer (SOL) that leads
to tolerable heat and particle loads on the wall is a major challenge. The new European …

Computational challenges in magnetic-confinement fusion physics

A Fasoli, S Brunner, WA Cooper, JP Graves, P Ricci… - Nature Physics, 2016 - nature.com
Magnetic-fusion plasmas are complex self-organized systems with an extremely wide range
of spatial and temporal scales, from the electron-orbit scales (∼ 10− 11 s,∼ 10− 5 m) to the …

Edge-localized-modes in tokamaks

AW Leonard - Physics of Plasmas, 2014 - pubs.aip.org
Edge-localized-modes (ELMs) are a ubiquitous feature of H-mode in tokamaks. When
gradients in the H-mode transport barrier grow to exceed the MHD stability limit the ELM …

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 …

Progress on the application of ELM control schemes to ITER scenarios from the non-active phase to DT operation

A Loarte, G Huijsmans, S Futatani, LR Baylor… - Nuclear …, 2014 - iopscience.iop.org
Progress in the definition of the requirements for edge localized mode (ELM) control and the
application of ELM control methods both for high fusion performance DT operation and non …

Heuristic drift-based model of the power scrape-off width in low-gas-puff H-mode tokamaks

RJ Goldston - Nuclear Fusion, 2011 - iopscience.iop.org
A heuristic model for the plasma scrape-off width in low-gas-puff tokamak H-mode plasmas
is introduced. Grad B and curv B drifts into the scrape-off layer (SOL) are balanced against …

A long-pulse high-confinement plasma regime in the Experimental Advanced Superconducting Tokamak

J Li, HY Guo, BN Wan, XZ Gong, YF Liang, GS Xu… - Nature physics, 2013 - nature.com
High-performance and long-pulse operation is a crucial goal of current magnetic fusion
research. Here, we demonstrate a high-confinement plasma regime known as an H-mode …

Partial detachment of high power discharges in ASDEX Upgrade

A Kallenbach, M Bernert, M Beurskens, L Casali… - Nuclear …, 2015 - iopscience.iop.org
Detachment of high power discharges is obtained in ASDEX Upgrade by simultaneous
feedback control of core radiation and divertor radiation or thermoelectric currents by the …

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 …