Resonant magnetic perturbations of edge-plasmas in toroidal confinement devices
TE Evans - Plasma Physics and Controlled Fusion, 2015 - iopscience.iop.org
Controlling the boundary layer in fusion-grade, high-performance, plasma discharges is
essential for the successful development of toroidal magnetic confinement power generating …
essential for the successful development of toroidal magnetic confinement power generating …
A full tungsten divertor for ITER: Physics issues and design status
RA Pitts, S Carpentier, F Escourbiac, T Hirai… - Journal of Nuclear …, 2013 - Elsevier
Budget restrictions have forced the ITER Organization to reconsider the baseline divertor
strategy, in which operations would begin with carbon (C) in the high heat flux regions …
strategy, in which operations would begin with carbon (C) in the high heat flux regions …
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 …
to tolerable heat and particle loads on the wall is a major challenge. The new European …
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 …
gradients in the H-mode transport barrier grow to exceed the MHD stability limit the ELM …
Progress on the application of ELM control schemes to ITER scenarios from the non-active phase to DT operation
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 …
application of ELM control methods both for high fusion performance DT operation and non …
Physics basis and design of the ITER plasma-facing components
RA Pitts, S Carpentier, F Escourbiac, T Hirai… - Journal of Nuclear …, 2011 - Elsevier
In ITER, as in any tokamak, the first wall and divertor plasma-facing components (PFC) must
provide adequate protection of in-vessel structures, sufficient heat exhaust capability and be …
provide adequate protection of in-vessel structures, sufficient heat exhaust capability and be …
Surface heat loads on the ITER divertor vertical targets
JP Gunn, S Carpentier-Chouchana, F Escourbiac… - Nuclear …, 2017 - iopscience.iop.org
The heating of tungsten monoblocks at the ITER divertor vertical targets is calculated using
the heat flux predicted by three-dimensional ion orbit modelling. The monoblocks are …
the heat flux predicted by three-dimensional ion orbit modelling. The monoblocks are …
ELM control strategies and tools: status and potential for ITER
Operating ITER in the reference inductive scenario at the design values of I p= 15 MA and Q
DT= 10 requires the achievement of good H-mode confinement that relies on the presence …
DT= 10 requires the achievement of good H-mode confinement that relies on the presence …
Observation of Lobes near the Point in Resonant Magnetic <?format ?>Perturbation Experiments on MAST
The application of nonaxisymmetric resonant magnetic perturbations (RMPs) with a toroidal
mode number n= 6 in the MAST tokamak produces a significant reduction in plasma energy …
mode number n= 6 in the MAST tokamak produces a significant reduction in plasma energy …
Advances in the physics understanding of ELM suppression using resonant magnetic perturbations in DIII-D
Recent experiments on DIII-D have increased confidence in the ability to suppress edge-
localized modes (ELMs) using edge-resonant magnetic perturbations (RMPs) in ITER …
localized modes (ELMs) using edge-resonant magnetic perturbations (RMPs) in ITER …