Conference Papers

Showing 1 - 10 of 16 Conference Paper Results
2020
UKAEA-CCFE-CP(20)119
12th IAEA Technical Meeting on Control, Data Acquisition and Remote Participation for Fusion Research, Daejeon, Republic of Korea, 13-17 May 2019

The JET control and data acquisition system (CODAS) is an integrated system that provides all the pulse based and continuous data acquisition, real time and slow control and control room interfaces for JET. It has a long history, dating back to the beginning of JET in 1980. It utilises both commercially available hardware along with many in-house m…

Preprint Published
2020
UKAEA-CCFE-CP(20)111
30th Symposium on Fusion Technology (SOFT), Giardini Naxos, Messina, Sicily, 16-21 September 2018

The Mega Amp Spherical Tokamak (MAST) is currently being extensively upgraded to provide a system that will be able to add to the knowledge base for ITER as well as testing innovative reactor systems such as the Super-X divertor. MAST-U will have increased coil system and power supply capability. Therefore, to ensure operation of MAST-U within safe…

Preprint Published
2020
UKAEA-CCFE-CP(20)103
24th International Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI), South Korea, 24 - 29 January 2021

One of the issues faced by future fusion devices will be high target heat loads. Alternative divertors are a potential solution to the heat loads. They have been investigated in TCV and DIII-D, and will be investigated on MAST-U. To evaluate their effectiveness, accurate target heat flux and power balance measurements are required in these machines…

Preprint Published
2020
UKAEA-CCFE-CP(20)101
46th European Physical Society Conference on Plasma Physics (EPS), Milan, 8-12 July 2019

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 Published
2020
UKAEA-CCFE-CP(20)100
46th European Physical Society Conference on Plasma Physics (EPS), Milan, 8-12 July 2019

Disruption prediction and avoidance is necessary in future MAST-U spherical tokamak discharges to enable long-pulse plasma operation. Research examining the stability of plasmas in the MAST database utilizing proposed high quality kinetic equilibrium reconstructions and calculations with various codes, including the Disruption Event Characterizatio…

Preprint Published
2018
UKAEA-CCFE-CP(20)77
30th Symposium on Fusion Technology (SOFT), Giardini Naxos, Messina, Sicily, 16-21 September 2018

Neutral beam injection is one of the primary auxiliary heating systems for tokamak plasmas. Once the neutral beam leaves the neutraliser collisions with background neutral particles in the beamline and tokamak vessel re-ionises part of the neutral beam. These particles can be deflected by the tokamak magnetic field, potentially damaging unshielded …

Preprint Published
2020
UKAEA-CCFE-CP(19)47
46th European Physical Society Conference on Plasma Physics (EPS), Milan, 8-12 July 2019

Spherical Tokamaks (STs) could provide a route towards a compact fusion reactor due to advantageous properties such as high plasma beta. A GW-scale ST plasma is explored where Q=10 and R=2.5m. In this design 110 MW of NBI is needed to provide 9 MA of noninductive current, where the remaining 12 MA is pressure driven. To penetrate into the core a 1 …

Preprint Published
2019
UKAEA-CCFE-CP(19)53
46th European Physical Society Conference on Plasma Physics (EPS), Milan, 8-12 July 2019

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 Published
2019
UKAEA-CCFE-CP(19)45
14th International Symposium on Fusion Nuclear Technology (ISFNT-14) Budapest,Hungary, 22-27 September 2019

Spherical Tokamaks offer a number of potential advantages for a future fusion power plant. They have a high ratio of thermal to magnetic field pressure (beta) and strong flows, either of which could result in reduced turbulence. Fewer Toroidal Field (TF) coils and a different geometry offers the potential for new methods of remote maintenance …

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The published version of this paper is currently under embargo and will be available on 14/02/2022
2019
UKAEA-CCFE-CP(19)44
12th IAEA Technical Meeting on Control, Data Acquisition and Remote Participation for Fusion Research, Daejeon, Republic of Korea, 13-17 May 2019

MAST has undergone a substantial upgrade [1], featuring among other things several new poloidal field coils mostly distributed around the new closed-throat divertor structure and an enlarged centre column. The considerable changes have required the plasma control software to be substantially re-written. The MAST digital plasma control system […

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