Conference Papers

Showing 1 - 10 of 79 Conference Paper Results
2019
UKAEA-RACE-CP(19)04
CASE 2019 - International Conference on Automation Science and Engineering, University of British Columbia, Vancouver, BC, Canada, 22- 26 August 2019

The extreme environmental conditions inside future nuclear fusion power plants will mean that maintenance activities must be performed without human access. Current teleoperation paradigms do not enable sufficiently fast maintenance cycles, and automation is seen as a potential solution. Transitioning to an automated maintenance scheme will requ…

Preprint
2019
UKAEA-CCFE-CP(19)57
14th International Reflectometry Workshop, Swiss Plasma Center of the Ecole Polytechnique Fédérale de Lausanne, Switzerland, 22-24 May 2019

All density profile reconstruction techniques for both O-mode and X-mode are based on the assumption that the cut-off frequency profile is monotonic. However, there are many sources of perturbations to the plasma that generate hollow areas in the cut-off frequency profile, breaking the aforementioned assumption. This causes a significant immediate …

Preprint
2020
UKAEA-CCFE-CP(20)01
149th Annual Meeting & Exhibition of the Minerals, Metals and Materials Society, San Diego, USA, 23 - 27 February 2020

The United Kingdom Atomic Energy Authority are involved in the design and manufacture of the diagnostic windows for ITER. ITER is an international project, with 35 nations collaborating to design, construct and operate a prototype controlled nuclear fusion reactor in southern France. As well as providing line of sight for diagnostics, the window…

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2019
UKAEA-CCFE-CP(19)56
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…

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The published version of this paper is currently under embargo and will be available on 03/01/2021
2019
UKAEA-CCFE-CP(19)55
14th International Reflectometry Workshop, Swiss Plasma Center of the Ecole Polytechnique Fédérale de Lausanne, Switzerland, 22-24 May 2019

The use of Doppler Backscattering (DBS) in spherical tokamaks is challenging since the magnetic pitch angle can be large (up to 35, compared to 15 in standard tokamaks like JET). Moreover the pitch angle varies both spatially and temporally. Hence, the probe beam is generally not perpendicular to the magnetic field. This misalignment, which affec…

Preprint
2019
UKAEA-CCFE-CP(19)54
28th IEEE Symposium on Fusion Engineering, Jacksonville, Florida, USA, 2 – 6 June 2019

Protecting the divertor in a nuclear fusion power plant is a key criteria for operation. Detailed divertor and scrape-off-layer (SOL) modelling is computationally intensive and unsuitable for a systems code. For the use of such models in systems codes they need to be simplified and made computationally fast, while still capturing the most important…

Preprint
2019
UKAEA-RACE-CP(19)04
14th International Symposium on Fusion Nuclear Technology (ISFNT-14) Budapest,Hungary, 22-27 September 2019

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…

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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
2019
UKAEA-CCFE-CP(19)52
46th European Physical Society Conference on Plasma Physics (EPS), Milan, 8-12 July 2019

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, the…

Preprint