D.B. King R. Sharma C.D. Challis A. Bleasdal E.G. Delabie D. Douai D. Keeling E. Lerche M.Lennholm J. Mailloux G. Matthews M. Nicassio Z. Stancar T. Wilson
Neutral Beam Injection (NBI) is a flexible auxiliary heating method for tokamak plasmas, capable of being efficiently coupled to the various plasma configurations required in the Tritium and mixed DeuteriumTritium Experimental campaign (DTE2) on the JET device. High NBI power was required for high fusion yield and alpha particle studies and to …
Preprint PublishedG. Qin H. Wu C. Li A. Ji S. Budden
The hybrid kinematic mechanism (HKM) as a remote handling subsystem of Demonstration Fusion Power Plant (DEMO) breeding blanket (BB) is undergoing extensive theoretical analysis and feasibility verification. In this paper, the forward and inverse kinematic models of HKM are respectively developed by combining the Newtonian iterative method and the …
PublishedWilliam Iliffe Simon Chislett-McDonald Fiona Harden Kirk Adams James Tufnail Chris Grovenor Susannah Speller Aidan Reilly Ezzat Nasr
The UKAEA’s Spherical Tokamak for Energy Production (STEP) program aims to demonstrate the ability of a low aspect ratio tokamak to generate net electricity from deuterium-tritium fusion. Specifically, its aim is to deliver a prototype fusion power plant, targeting 2040, and a path to the commercial viability of fusion, by engaging with and invig…
PreprintJ. O. Allen S. Desai S. Freethy K. Hawkins M. A. Henderson E. Kaijanen C. Lechte J. Lovell E. Melidis A. Munasinghe J. Pearl B. Plaum A. Seidu H. Webster the MAST-U EBW Team
MAST-Upgrade (MAST-U) is undergoing several enhancements to deliver increased performance and functionality. One such enhancement is the design, development, and implementation of an Electron Bernstein Wave (EBW) Heating and Current Drive (HCD) System. The MAST-U EBW System aims to provide experimental data for model validation, and to provide a…
PreprintChris Brown Hanni Lux James Cowan
Developments in fusion energy technology and the aspiration to build and run commercial fusion energy power plants has seen the commencement of numerous publicly and privately funded projects in recent years. Megaprojects, like fusion power plants, by their very nature are inherently complex and risky, therefore providing a robust cost estimate in …
PreprintE. Parr K. G. McClements W. W. Heidbrink C. Michael G. Prechel J. Rivero-Rodriguez
A method for determining the fast-ion population density in magnetically-confined plasmas as a function of radius-pitch values, (R, Lambda), using ssNPA-signal and NBI power-output data has been developed. Oscillations in the NBI power output are replicated only in the active part of the ssNPA signal, allowing this to be separated…
PreprintJ W Berkery S A Sabbagh C Ham V Zamkovska J Butt J Riquezes M Tobin S Henderson L Kogan B Patel R Scannell E Trier B LeBlanc
Fusion power output from spherical tokamaks would benefit from increased confined plasma density, but there exists a limit on the density before confinement is lost and the plasma current is disrupted. This density limit has long been characterized by a simple, global Greenwald limit proportional to the plasma current and inversely proportional …
Preprint PurchaseDaniel Padrão David Hancock James Paterson Frank Schoofs Christopher Tuck Ian Maskery
Heat sinks have manifold applications, from micro-electronics to nuclear fusion reactors. Their performance expectations will continue to increase in line with the power consumption and miniaturisation of technology. Additive manufacturing enables the creation of novel, compact heat sinks with greater surface-to-volume ratios and geometrical comple…
Preprint PublishedP.-Y. Li D. R. Hatch B. Chapman-Oplopoiou S. Saarelma C. M. Roach M. Kotschenreuther S. M. Mahajan the MAST Team
The results of a recent gyrokinetic analysis of turbulent transport driven by the electron temperature gradient (ETG) in the MAST pedestal are presented. During the inter-ELM period, the buildup rate of the electron density gradients is faster than that of the electron temperature gradients, possibly indicating the presence of an active electron th…
PreprintO. P. Bardsley J. L. Baker
Power exhaust is a critical challenge for spherical tokamak reactors, making the design, optimisation and control of advanced divertor configurations crucial. These tasks are greatly simplified if the poloidal magnetic fields in the core and divertor regions can be varied independently. We present a novel method which fixes the core plasma equil…
Preprint Published