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UKAEA-CCFE-PR(23)1822023
The reference ion cyclotron resonance frequency (ICRF) heating schemes for ITER deuterium-tritium (D-T) plasmas at the full magnetic field of 5.3 T are second harmonic heating of tritium and 3He minority heating. The wave-particle resonance location for these schemes coincide and are central at a wave frequency of 53 MHz at 5.3T [1]. Experiments ha…
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UKAEA-CCFE-PR(23)1702023
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 …
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UKAEA-CCFE-PR(23)1682023
Wide-spread availability of low-cost digital sensors has made the acquisition of full-field experimental measurements less challenging, with modern measurement systems capable of obtaining three dimensional (3D) data fields. This presents difficulties when comparing computational and co…
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UKAEA-RACE-PR(23)052023
ITER In-Vessel Components (IVCs) will have limited lifetimes and need to be maintained and/or replaced during the operational life of ITER. IVCs are attached to the plant cooling water system via pipework to enable active cooling of the components during plasma operations. When maintenance is required, Remote Handling Systems (RHS) will be used …
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UKAEA-RACE-PR(23)042023
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 …
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UKAEA-STEP-CP(23)112023
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…
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UKAEA-CCFE-PR(23)1642023
The present paper is dedicated to the study of the discrepancies encountered in electron temperatures (Te) measurements carried out with Electron Cyclotron Emission (ECE) and Thomson Scattering (TS) diagnostics in the core of the JET tokamak. A large database of discharges has been collected, including high-performance scenarios perform…
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UKAEA-CCFE-CP(23)642023
The fusion reaction between deuterium and tritium, D(T,n)4He is the main source of energy in future thermonuclear reactors. Charged fusion products of this reaction, α-particles (4He-ions), are born with an average energy of 3.5 MeV. Transferring energy to the thermal plasma during their slowing down, the…
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UKAEA-CCFE-CP(23)622023
The UK National Nuclear Laboratory (NNL) has been developing its capability in high‑temperature water corrosion over the past years in collaboration with the University of Bristol, UK. As part of this work, studies have been undertaken on nuclear fusion‑specific material Eurofer‑97, a reduced activation ferritic‑martensitic steel. Eurofe…
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UKAEA-CCFE-PR(23)1532023
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…
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