A review of modelling and simulation of hydrogen behaviour in tungsten at different scales
GH Lu, HB Zhou, CS Becquart - Nuclear Fusion, 2014 - iopscience.iop.org
Tungsten (W) is considered to be one of the most promising plasma-facing materials (PFMs)
for next-step fusion energy systems. However, as a PFM, W will be subjected to extremely …
for next-step fusion energy systems. However, as a PFM, W will be subjected to extremely …
Pellet injection experiments and modelling
B Pégourié - Plasma Physics and Controlled Fusion, 2007 - iopscience.iop.org
During the last decade, significant progress has been made in the field of pellet injection
with (1) the identification of the drift of the deposited material in the inhomogeneous …
with (1) the identification of the drift of the deposited material in the inhomogeneous …
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 …
Suppression of large edge localized modes in high confinement DIII-D plasmas with a stochastic magnetic boundary
Large 70Hz Type-I edge localized modes (ELMs) are converted into small 130Hz
oscillations using edge resonant magnetic perturbations (RMPs) from a coil with currents⩽ …
oscillations using edge resonant magnetic perturbations (RMPs) from a coil with currents⩽ …
Recent analysis of key plasma wall interactions issues for ITER
J Roth, E Tsitrone, A Loarte, T Loarer… - Journal of nuclear …, 2009 - Elsevier
Plasma wall interaction (PWI) is important for the material choice in ITER and for the plasma
scenarios compatible with material constraints. In this paper, different aspects of the PWI are …
scenarios compatible with material constraints. In this paper, different aspects of the PWI are …
Assessment of erosion of the ITER divertor targets during type I ELMs
G Federici, A Loarte, G Strohmayer - Plasma physics and …, 2003 - iopscience.iop.org
This paper presents the results of a preliminary assessment conducted to estimate the
thermal response and erosion lifetime of the ITER divertor targets clad either with carbon …
thermal response and erosion lifetime of the ITER divertor targets clad either with carbon …
ELM pace making and mitigation by pellet injection in ASDEX Upgrade
PT Lang, GD Conway, T Eich, L Fattorini… - Nuclear …, 2004 - iopscience.iop.org
In ASDEX Upgrade, experimental efforts aim to establish pace making and mitigation of type-
I edge localized modes (ELMs) in high confinement mode (H-mode) discharges. Injection of …
I edge localized modes (ELMs) in high confinement mode (H-mode) discharges. Injection of …
Tungsten: an option for divertor and main chamber plasma facing components in future fusion devices
The tungsten programme in ASDEX Upgrade is pursued towards a full high-Z device. The
spectroscopic diagnostic of W has been extended and refined and the cooling factor of W …
spectroscopic diagnostic of W has been extended and refined and the cooling factor of W …
Conceptual design study for heat exhaust management in the ARC fusion pilot plant
The ARC pilot plant conceptual design study has been extended beyond its initial scope [BN
Sorbom et al., FED 100 (2015) 378] to explore options for managing∼ 525 MW of fusion …
Sorbom et al., FED 100 (2015) 378] to explore options for managing∼ 525 MW of fusion …
Plasma detachment in linear devices
N Ohno - Plasma Physics and Controlled Fusion, 2017 - iopscience.iop.org
Plasma detachment research in linear devices, sometimes called divertor plasma
simulators, is reviewed. Pioneering works exploring the concept of plasma detachment were …
simulators, is reviewed. Pioneering works exploring the concept of plasma detachment were …