Overview of JET results for optimising ITER operation

J Mailloux, N Abid, K Abraham, P Abreu… - Nuclear …, 2022 - iopscience.iop.org
The JET programme in 2019–2020 focussed on preparing for the exploitation of JET's
currently unique capabilities, tritium handling and ITER-like wall (ILW: Be first wall and W …

Physics of ultimate detachment of a tokamak divertor plasma

SI Krasheninnikov, AS Kukushkin - Journal of Plasma Physics, 2017 - cambridge.org
The basic physics of the processes playing the most important role in divertor plasma
detachment is reviewed. The models used in the two-dimensional edge plasma transport …

The JET hybrid scenario in deuterium, tritium and deuterium-tritium

J Hobirk, CD Challis, A Kappatou, E Lerche… - Nuclear …, 2023 - iopscience.iop.org
The JET hybrid scenario has been developed from low plasma current carbon wall
discharges to the record-breaking Deuterium-Tritium plasmas obtained in 2021 with the …

Overview of the JET preparation for deuterium–tritium operation with the ITER like-wall

E Joffrin, S Abduallev, M Abhangi, P Abreu… - Nuclear …, 2019 - iopscience.iop.org
Since 2016, the JET scientific programme is engaged in a multi-campaign effort including
experiments in D, H and T [1], leading to 2020 and the first experiments with 50%/50% D–T …

Overview of the JET results in support to ITER

X Litaudon, S Abduallev, M Abhangi, P Abreu… - Nuclear …, 2017 - iopscience.iop.org
The European nuclear fusion research community has elaborated a Roadmap to the
realisation of fusion energy in which 'ITER is the key facility and its success is the most …

Erosion, screening, and migration of tungsten in the JET divertor

S Brezinsek, A Kirschner, M Mayer… - Nuclear …, 2019 - iopscience.iop.org
The erosion of tungsten (W), induced by the bombardment of plasma and impurity particles,
determines the lifetime of plasma-facing components as well as impacting on plasma …

Advances in understanding of high-Z material erosion and re-deposition in low-Z wall environment in DIII-D

R Ding, DL Rudakov, PC Stangeby… - Nuclear …, 2017 - iopscience.iop.org
Dedicated DIII-D experiments coupled with modeling reveal that the net erosion rate of high-
Z materials, ie Mo and W, is strongly affected by carbon concentration in the plasma and the …

Plasma–tungsten interactions in experimental advanced superconducting tokamak (EAST)

F Ding, GN Luo, X Chen, H Xie, R Ding, C Sang, H Mao… - Tungsten, 2019 - Springer
Tungsten (W) is used as the armor material of the International Thermonuclear Experimental
Reactor (ITER) divertor and is regarded as the potential first wall material of future fusion …

New H-mode regimes with small ELMs and high thermal confinement in the Joint European Torus

J Garcia, E De La Luna, M Sertoli, FJ Casson… - Physics of …, 2022 - pubs.aip.org
New H-mode regimes with high confinement, low core impurity accumulation, and small
edge-localized mode perturbations have been obtained in magnetically confined plasmas at …

Advances in the long-pulse steady-state high beta H-mode scenario with active controls of divertor heat and particle fluxes in EAST

BN Wan, XZ Gong, Y Liang, N Xiang, GS Xu… - Nuclear …, 2022 - iopscience.iop.org
Since the last IAEA-Fusion Energy Conference, the Experimental Advanced
Superconducting Tokamak (EAST) research program has been, in support of ITER and …