Conference Papers

Showing 51 - 60 of 260 Conference Paper Results
2022
UKAEA-CCFE-CP(23)38
6th CIRP Conference on Surface Integrity, Lyon, France, 8-10 June 2022

The high ductile-to-brittle transition temperature (DBTT) of tungsten combined with its high hardness make machining incredibly difficult. These properties typically result in the poor-quality machined surfaces and short tool life. In this study, TiAlN coated carbide tools with different rake angles (8°, 10° and 12°) were tested in convention…

Preprint
2022
UKAEA-STEP-CP(23)04
48th EPS Conference on Plasma Physics, Maastricht (Netherlands), June 27 to July 1 2022

The UK has launched a programme to build a prototype fusion power plant, the Spherical Tokamak for Energy Production (STEP), by 2040. It is intended that the STEP prototype will generate fusion power of the order of 1 GW and net electrical power of the order of 100 MW. Plasma scenarios that could be compatible with these design requirements and wit…

Preprint
2022
UKAEA-STEP-CP(23)05
21ST JOINT WORKSHOP ON ELECTRON CYCLOTRON EMISSION (ECE) AND ELECTRON CYCLOTRON RESONANCE HEATING (ECRH), ITER Headquarters, 20-24 June 2022

The UK’s Spherical Tokamak for Energy Production (STEP) reactor design program is now exclusively investigating concepts using microwave-based heating and current drive (HCD) systems. Electron Bernstein Wave (EBW) HCD is a relatively immature technology compared to Electron Cyclotron (EC) HCD but is of interest due to the promise of high current…

Preprint
2022
UKAEA-CCFE-CP(23)40
48th EPS Conference on Plasma Physics, Maastricht (Netherlands), June 27 to July 1 2022

Shattered pellet injection (SPI), with research started in recent years, is the current concept for the ITER disruption mitigation system (DMS) to prevent disruption-related damage. Compared with impurity SPI, pure deuterium (D2) SPI could contribute to runaway electron (RE) avoidance in ITER via a strong dilution cooling before the thermal quen…

Preprint
2022
UKAEA-STEP-CP(23)06
48th EPS Conference on Plasma Physics, Maastricht (Netherlands), June 27 to July 1 2022

The Spherical Tokamak for Energy Production (STEP) is a UKAEA program that aims to deliver a prototype fusion energy plant and a path to commercial viability of fusion [1]. The low aspect ratio spherical tokamak is attractive because of its potential to achieve high normalized beta βN operation, and the fusion power ~β…

Preprint
2022
UKAEA-RACE-CP(23)04
23rd Towards Autonomous Robotic Systems Conference (TAROS), RACE, UKAEA, 7-9 September 2022

This paper describes a novel automatic solution for toolchanging operations using dexterous teleoperated robots in a nuclear glovebox. This solution can identify and locate tools in the nuclear glovebox by visually tracking augmented reality (AR) tags online at a low computational cost. The solution is designed in a modular manner taking into ac…

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2022
UKAEA-CCFE-CP(23)41
48th EPS Conference on Plasma Physics, Maastricht (Netherlands), June 27 to July 1 2022

The MAST-U spherical tokamak has extensive capabilities to produce and explore strongly shaped plasmas and alternative divertor configurations, especially the Super-X. Robust and accurate reconstructions of plasma equilibria are the foundation of many physics analyses, as well as being important intershot for informing operation of the tokamak. …

Preprint
2021
UKAEA-CCFE-CP(23)20
28th IAEA Fusion Energy Conference, Nice, France, 10-15th May 2021

Disruption prediction and avoidance is critical for ITER and reactor-scale tokamaks to maintain steady plasma operation and to avoid damage to device components. The present status and results from the disruption event characterization and forecasting (DECAF) research effort are shown. The DECAF paradigm is primarily physics-based and provides q…

Preprint
2020
UKAEA-CCFE-CP(23)26
47th EPS Plasma Physics Virtual Conference, 21-25 June 2021

Observations of radiation in the ion cyclotron range of frequencies from the KSTAR tokamak and LHD heliotron-stellarator show that energetic neutral beam injected (NBI) ion populations can relax collectively in the edge plasma near the injection point. The resulting radiation is ion cyclotron emission (ICE), whose spectrum has strongly suprather…

Preprint
2021
UKAEA-CCFE-CP(23)21
PVP: Pressure Vessels & Piping, Virtual Conference, 13-16 July, 2021

Sandwich-type cooling pipes of the first wall of future fusion nuclear reactors (i.e. DEMO) will likely consist of tungsten brazed to a Reduced Activation Ferritic Martensitic (RAFM) steel. Under a high heat flux (HHF) (1-5 MW/m2) the mismatch in thermal expansion between tungsten and steel results in significant thermal stresses in the brazing …

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