Showing 1 - 6 of 6 Conference Paper Results
2020
UKAEA-CCFE-CP(20)98
27th IAEA Fusion Energy Conference, Ahmedabad, India, 22-27 October 2018
C. Giroud N. Aiba F. Militello C. Challis A. Chankin B. Lomanowski D. Hatch J. Harrison D. Frigione D. Moulton S. Pamela F. Parra J. Parisi I. Putzai D. Refy S. Saarelma C. Stavrou B. Tal E. Belonohy S. Brezinsek S. Buller C. Bowman E. Delabie A. Field J. Fontdecaba A. Huber A. Meigs S. Menmuir J. Simpson JET Contributors
Preprint
2020
UKAEA-CCFE-CP(20)72
27th IAEA Fusion Energy Conference, Ahmedabad, India, 22-27 October 2018
J.E. Menard R. Majeski M. Ono N.N. Bakharev V.K. Gusev M. Gryaznevich D. Kingham S. McNamara P. Thomas K. Hanada J. Harrison B. Lloyd Y.S. Hwang B. Lipschultz H. Wilson Y. Nagayama Y. Ono Y. Takase M. Reinke K. Tobita Z. Gao F. Alladio R.J. Fonck
The spherical torus/tokamak (ST) is a potentially attractive configuration for narrowing scientific and technical gaps to a fusion demonstration power plant and as a more compact and/or modular fusion power source. Due to a reduced plasma surface area to volume ratio, the ST configuration offers the potential to access high power exhaust heat fluxe…
Preprint2019
UKAEA-CCFE-CP(19)42
46th European Physical Society Conference on Plasma Physics (EPS), Milan, 8-12 July 2019
A. Fil B. Dudson B. Lipschultz D. Moulton O. Myatra K. Verhaegh O. Fevrier J. Harrison A. Thornton M. Wensing
Plasma detachment needs to be achieved in ITER [1] and future devices such as DEMO to dissipate most of the power in the Scrape-Off-Layer (SOL) and reduce the particle flux reaching the divertor targets. In order to enhance our capability to improve current, and design future tokamaks, we must improve our understanding of the relative effect on det…
Preprint Published2019
UKAEA-CCFE-CP(19)40
46th European Physical Society Conference on Plasma Physics (EPS), Milan, 8-12 July 2019
F. Militello R. Akers L. Appel B. Cannas S. Carcangiu B. Dudson A. Fanni T. Farley A. Kirk J.R. Harrison B. Lipshultz A. Montisci T. Nicholas J.T. Omotani F. Pisano F. Riva G. Sias N.R. Walkden A. Wynn the MAST JET5 teams
In magnetic confinement devices, boundary turbulence is responsible for transporting plasma and energy from the well-confined region towards the material surfaces where it can severely harm reactor relevant machines. It is therefore essential to develop a solid understanding of the mechanisms behind the transport in the edge of the plasma. Large fl…
Preprint Published2019
UKAEA-CCFE-CP(19)20
23rd International Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI), Princeton, NJ, USA, 17-22 June 2018
S. S. Henderson M. Bernert S. Brezinsek M. Carr M. Cavedon R. Dux D. S. Gahle J. Harrison B. Lipschultz B. Lomanowski A. Meigs M. O’Mullane F. Reimold M. L. Reinke S. Wiesen the EUROfusion MST1 team the ASDEX Upgrade team JET contributors
Reducing the plasma power exhaust impacting on plasma facing components during steady state operation is one of the major design issues in future tokamaks such as ITER. Impurity seeding, e.g. with N, is one method of achieving this and has been used for a long time in tokamak research [1]. In this work we exploit a recently developed spectroscopic …
Preprint Purchase2018
UKAEA-CCFE-CP(18)03
27th IAEA Fusion Energy Conference, Ahmedabad, India, 22-27 October 2018