C.D. Challis S. Brezinsek I. Coffey M. Fontana N. Hawkes D. Keeling D. King G. Pucella E. Viezzer JET Contributors
The initial current ramp phase of JET hybrid plasmas is used to optimise the target q-profile for main heating to allow access to high beta and avoid MHD instabilities. Mixed protium-deuterium experiments, carried out at JET since the installation of the beryllium-tungsten wall, have shown that the q-profile evolution during this Ohmic phase varies…
Preprint PublishedS.F. Smith S.J.P. Pamela M. Hölzl G.T.A. Huijsmans A. Kirk D. Moulton A.J. Thornton H.R. Wilson
During edge localised modes (ELMs) high heat fluxes are incident on divertor targets, which future fusion devices will not withstand [1]. A solution to reduce the heat fluxes could be the new Super-X divertor, which will be tested on the MAST-U tokamak. The divertor has an increased connection length, magnetic flux expansion and is designed to reta…
Preprint PublishedL. Piron T. C. Hender E. Joffrin F. Auriemma P. Buratti R. Paccagnella P. Zanca C. Challis S. Gerasimov R. B. Henriques L. Marrelli P. Lomas F. Rimini D. Terranova
The presence of Error Fields (EFs) in magnetic fusion devices can affect energy confinement and plasma stability by braking plasma rotation, by inducing fast particle losses and being amplified when exploring high-b regimes. The resulting EF Locked Modes (LMs) can be stabilized by NBI injection through the rotation shielding mechanism. However, …
Preprint PublishedM.S. Anastopoulos-Tzanis C.H. Ham H.R. Wilson
H-mode tokamak plasmas are typically characterised by quasi-periodic instabilities called edge localised modes (ELMs) driven by unstable peeling-ballooning modes [1]. For large scale fusion power plants, the predicted particle and heat fluxes are unacceptable, and an active ELM control method is required. One promising method relies on t…
Preprint PublishedK D Lawson M Groth D Harting S Menmuir D Reiter K M Aggarwal S Brezinsek I H Coffey G Corrigan F P Keenan C F Maggi A G Meigs M G O’Mullane S Wiesen JET Contributors
An understanding of the plasma edge and divertor is essential for predicting the performance of next-step machines such as ITER. Transport codes used to study the divertor behaviour [1] employ atomic physics data in two applications. The first is to predict the power radiated by the fuel and impurity atoms, which is carried out as a post-processing…
Preprint PublishedB. Cannas S. Carcangiu A. Fanni T. Farley F. Militello A. Montisci F. Pisano G. Sias N. Walkden
In the present magnetically confined plasmas, the prediction of particle loading on material surfaces is a primary concern in view of the protection of plasma facing components for next step devices. Thus, an understanding of filament dynamics is needed. In this context, this work aims to develop an automatic detector for filaments arising in the M…
Preprint PublishedN. Zhang Y. Q. Liu P. Piovesan V. Igochine D. L. Yu S. Wang G. Q. Dong G. Z. Hao G. L. Xia W. J. Chen L. Liu J. Q. Li X. Bai
Resistive plasma response to the n = 1 (n is the toroidal mode number) RMP field is systematically investigated for a high-beta hybrid discharge on ASDEX Upgrade. Both linear and quasi-linear response are modelled using the MARS-F and MARS-Q codes, respectively. Linear response computations show a large internal kink response when the plasma centra…
Preprint PublishedStefano Coda
The research program of the TCV tokamak ranges from conventional to advanced-tokamak scenarios and alternative divertor configurations, to exploratory plasmas driven by theoretical insight, exploiting the device’s unique shaping capabilities. Disruption avoidance by real-time locked mode prevention or unlocking with ECRH was thoroughly documen…
Preprint PublishedYu.V. Yakovenko V.V. Lutsenko B.S. Lepiavko V.Ya. Goloborodko Ya.I. Kolesnichenko A.I. Tishchenko V. Kiptily S. Sharapov L. Giacomelli T. Craciunescu H. Weisen JET Contributors
Results of simulations of the sawtooth-induced redistribution of fast ions in JET and ITER with the code OFSEF are presented. The dependence of the redistribution on the particle parameters (energy and pitch angle) is studied. The redistribution of the trapped and marginally passing particles is found to exhibit barrier-like behaviour at the separa…
Preprint PublishedS. A. Silburn G. F. Matthews T. W. Morgan R. E. Nygren the Magnum PSI Team
Recent experiments on Magnum-PSI exposed a lithium-filled heat pipe to a hydrogen plasma beam to demonstrate the potential of radiatively cooled, high temperature heat pipes as modular, replaceable plasma facing components. Monitoring the temperature distribution over the full 20cm length of the pipe was a crucial element of the experiment, requiri…
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