V.G. Kiptily M. Fitzgerald S.E. Sharapov M. Poradzinski Z. Stancar P. J. Bonofiglo R. Dumont Z. Ghani V. Goloborodko S. Menmuir1 D. Keeling M. Podestà H. Sun D.M. Taylor D. Douai J. Garcia C.F. Maggi J. Mailloux F. Rimini
The fusion-born alpha-particle heating in magnetically confined fusion machines is a high priority subject for study. The self-heating of thermonuclear fusion plasma by alpha-particles was observed in recent deuterium-tritium (D-T) experiments on the Joint European Torus (JET). This observation was possible by conducting so-called “after…
PreprintH. Wu P. Shi F. Subba H. Sun M. Wischmeier R. Zanino the ASDEX Upgrade Team
The High Field High Density Region (HFSFD) has been experimentally observed in both divertor and limiter tokamak devices. In order to numerically reproduced the HFSHD region in the limiter tokamak device J-TEXT, we first performed SOLPS-ITER simulations on the J-TEXT limiter tokamak with the activation of drifts, which is associated with the HFSHD …
PreprintHJ. Sun SA. Silburn IS. Carvalho C Giroud G Fishpool GF. Matthews DB. King RB. Henriques DL. Keeling FG. Rimini L. Garzotti D. Frigione D. Van Eester D Kos M-L. Mayoral J. Mailloux C. Maggi A. Huber D. Douai PJ. Lomas L Morten M. Maslov K. Kirov P. Jacquet CG. Lowry M. Baruzzo C. Stuart J. Mitchell L. Horvath DC. McDonald JET Contributors
Unusually high power loads on the Beryllium limiter caused by Neutral Beam re-ionisation, and much cooler divertor target surfaces were observed during the recent JET tritium campaign. As both phenomena are driven by scrape-off layer (SOL) physics, the SOL features of 72 tritium H-mode discharges and their deuterium references have been studied. …
Preprint PublishedH. J. Sun R. J. Goldston A. Huber X. Q. Xu J. Flanagan D. C. McDonald E. de la Luna M. Maslov J. R. Harrison F. Militello J. Fessey S. Cramp JET Contributors
A study of a dataset of JET H-mode plasma with the Be/W ITER-like wall (JET-ILW) shows that reaching the edge MHD ballooning limit leads to confinement degradation. However, unlike JET plasmas with a carbon wall (JET-C), the JET-ILW plasmas stay in a marginal dithering phase for a relatively long period, associated with a higher (20%) H-mode den…
Preprint PublishedPeng Shi Hongjuan Sun Ge Zhuang Zhifeng Cheng Li Gao Zhipeng Chen Jingchun Li Yinan Zhou the J-TEXT Team
This article reports the first observation of the high-field side high density (HFSHD) in the limiter devices. In the J-TEXT high density discharges, the high-density front at the HFS scrape-off layer (SOL) region edge has been clearly identified by the far-infrared laser polarimeter-interferometer. The HFSHD forms at the HFS SOL, and then expan…
Preprint PublishedS.N. Gerasimov P. Abreu L.R. Baylor A. Boboc I.S. Carvalho I.H. Coffey D. Craven V. Huber S. Jachmich E. Joffrin U. Kruezi M. Lehnen P.J. Lomas A. Manzanares M. Maslov E. Matveeva G. Pautasso A. Peacock S. Silburn C. Stuart H. Sun D. Shiraki R. Sweeney J. Wilson L.E. Zakharov
The disruption mitigation system at ITER will include four shattered pellet injectors (SPI), which will be dedicated to the mitigation of electro-magnetic loads (EML), thermal loads and the avoidance and suppression of runaway electrons. Recently the JETILW was equipped with an SPI with a wide capability. Specifically: pellet diameter d = [4.57, 8.…
PreprintH. J. Sun E. Wolfrum T. Eich A. Kallenbach P. Schneider B. Kurzan U. Stroth the ASDEX Upgrade Team
A survey of the correlation between temperature and density gradient lengths ( and ) has been performed for the near SOL regions in the ASDEX Upgrade tokamak. In common with previous studies, the near SOL temperature and density gradient length ratio, , is found to be close to unity across a wide range of plasmas. However, it is found that it is po…
Preprint PublishedH. J. Sun RJ. Goldston A.Huber XQ. Xu J. Flanagan DC. McDonald E. de la Luna M. Maslov J. Harrison F. Militello J. Fessy S. Cramp JET Contributors
A study of a dataset of JET plasma with the Be/W ITER-like wall (JET-ILW) shows that reaching the edge MHD ballooning limit leads to confinement degradation. However, unlike JET plasma with a carbon wall (JET-C), the JET-ILW plasma stays in a marginal dithering phase for a relatively long period, associated with a higher a ( 20%) H-mode density lim…
Preprint PublishedDominic C Calleja Wayne Arter Marco De-Angelis Edoardo Patelli
Nuclear fusion, the process by which the Sun generates energy, is proposed as one solution to secure the future of global energy supply. If successful it will provide an unlimited source of clean energy. Probably the most promising approach to harnessing fusion for energy production is that of the Tokamak device, a magnetic confinement device of to…
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