Physics basis for the first ITER tungsten divertor
On the eve of component procurement, this paper discusses the present physics basis for
the first ITER tungsten (W) divertor, beginning with a reminder of the key elements defining …
the first ITER tungsten (W) divertor, beginning with a reminder of the key elements defining …
A brief history of negative triangularity tokamak plasmas
A Marinoni, O Sauter, S Coda - Reviews of Modern Plasma Physics, 2021 - Springer
This review is devoted to tokamak plasmas with a cross sectional shape featuring negative
triangularity, which appear to hold great promise as a candidate reactor configuration owing …
triangularity, which appear to hold great promise as a candidate reactor configuration owing …
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 …
Physics and technology considerations for the deuterium–tritium fuel cycle and conditions for tritium fuel self sufficiency
The tritium aspects of the DT fuel cycle embody some of the most challenging feasibility and
attractiveness issues in the development of fusion systems. The review and analyses in this …
attractiveness issues in the development of fusion systems. The review and analyses in this …
The influence of plasma-surface interaction on the performance of tungsten at the ITER divertor vertical targets
G De Temmerman, T Hirai, RA Pitts - Plasma Physics and …, 2018 - iopscience.iop.org
The tungsten (W) material in the high heat flux regions of the ITER divertor will be exposed
to high fluxes of low-energy particles (eg H, D, T, He, Ne and/or N). Combined with long …
to high fluxes of low-energy particles (eg H, D, T, He, Ne and/or N). Combined with long …
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 …
[HTML][HTML] ELM divertor peak energy fluence scaling to ITER with data from JET, MAST and ASDEX upgrade
A newly established scaling of the ELM energy fluence using dedicated data sets from JET
operation with CFC & ILW plasma facing components (PFCs), ASDEX Upgrade (AUG) …
operation with CFC & ILW plasma facing components (PFCs), ASDEX Upgrade (AUG) …
Gyrokinetic analysis and simulation of pedestals to identify the culprits for energy losses using 'fingerprints'
Fusion performance in tokamaks hinges critically on the efficacy of the edge transport barrier
(ETB) in suppressing energy losses. The new concept of'fingerprints' is introduced to identify …
(ETB) in suppressing energy losses. The new concept of'fingerprints' is introduced to identify …
Physics conclusions in support of ITER W divertor monoblock shaping
The key remaining physics design issue for the ITER tungsten (W) divertor is the question of
monoblock (MB) front surface shaping in the high heat flux target areas of the actively cooled …
monoblock (MB) front surface shaping in the high heat flux target areas of the actively cooled …
Pedestal bifurcation and resonant field penetration at the threshold of edge-localized mode suppression in the DIII-D tokamak
R Nazikian, C Paz-Soldan, JD Callen, JS DeGrassie… - Physical review …, 2015 - APS
Rapid bifurcations in the plasma response to slowly varying n= 2 magnetic fields are
observed as the plasma transitions into and out of edge-localized mode (ELM) suppression …
observed as the plasma transitions into and out of edge-localized mode (ELM) suppression …