Showing 1 - 8 of 8 Conference Paper Results
2021
UKAEA-CCFE-CP(21)02
24th International Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI), South Korea, 24 - 29 January 2021
J. Leland S. Elmore A. Kirk H. v/d Meiden. J. Scholten S. Allan J. W. Bradley
Measurements made using flush-mounted Langmuir probes (FMPs) in tokamaks are difficult to interpret when operating at grazing angles of magnetic field incidence due to the effects of sheath expansion on the probe collection area. The super-X divertor on the upgraded Mega Ampere Spherical Tokamak (MAST-U) will have very shallow angles of magnetic fi…
Preprint Purchase2020
UKAEA-CCFE-CP(20)101
46th European Physical Society Conference on Plasma Physics (EPS), Milan, 8-12 July 2019
S.A. Sabbagh J.W. Berkery A. Kirk Y.S. Park J.H. Ahn J.M. Bialek Y. Jiang J.D. Riquezes J.G. Bak K. Erickson A.H. Glasser C. Ham J. Hollocombe J. Kim J. Ko W.H. Ko L. Kogan J.H. Lee A. Thornton S.W. Yoon Z.R. Wang
Disruption prediction and avoidance is critical in ITER and reactor-scale tokamaks to maintain steady plasma operation and to avoid damage to device components. The present status and results from the physics-based disruption event characterization and forecasting (DECAF) research effort are shown for multiple tokamak devices. Present analysis of K…
Preprint Published2019
UKAEA-RACE-CP(19)04
14th International Symposium on Fusion Nuclear Technology (ISFNT-14) Budapest,Hungary, 22-27 September 2019
T. Tremethick S. Kirk K. Keogh A. O’Hare E. Harford B. Quirk
As part of the European Research Roadmap to the Realisation of Fusion Energy, the DEMO reactor aims to show the feasibility of a fusion power plant. Due to the loss of revenue created by downtime and the potential for a breakdown to render a reactor inoperable, maintenance is “mission critical” for a power plant. The harsh environment of a fusi…
Preprint Purchase2019
UKAEA-CCFE-CP(19)53
46th European Physical Society Conference on Plasma Physics (EPS), Milan, 8-12 July 2019
S.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 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)16
45th European Physical Society Conference on Plasma Physics (EPS), Prague, 2-6 July 2018
D A Ryan L Piron A Kirk Y Q Liu M Dunne L Li B Dudson W Suttrop the ASDEX Upgrade team the EUROfusion MST1 team
Edge Localised Modes (ELMs) in H-mode tokamak plasmas may be controlled or entirely suppressed by applying 3D magnetic perturbations (MPs). The applied perturbation is amplified by the plasma response, and it has previously been established that the size of the peeling component of this response is a reliable indicator for expected ELM control on A…
Preprint2019
UKAEA-CCFE-CP(19)01
Waste Management Symposia (WMS), Phoenix, USA, 18-22 March 2018
S. Kirk K. Keogh W. Suder T. Tremethick C. Allen I. Farquhar
The maintenance, replacement and decommissioning of future nuclear fusion reactors will require quick and reliable cutting and joining of in-vessel pipework. Initial design studies for nuclear fusion reactors for power generation have estimated cutting and welding could account for up to 60% of the maintenance duration using conventional in-situ pr…
Preprint Published2018
UKAEA-CCFE-CP(18)05
45th European Physical Society Conference on Plasma Physics (EPS), Prague, 2-6 July 2018