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UKAEA-CCFE-PR(25)3322025
Lithium oxide is an important candidate material for tritium breeding in fusion nuclear reactors. Here we assess the disorder created in Li2O on bombardment by high-energy neutrons, examining the mechanisms of recovery and the…
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2025
AC losses in the high temperature superconducting (HTS) toroidal field (TF) magnets of the STEP tokamak are analysed, focusing on the transient electromagnetic response of the centre column to the charging and discharging of the central solenoid (CS) and poloidal field (PF) magnets during a plasma initiation scenario. An innovative H-H…
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UKAEA-CCFE-PR(25)3262024
In this paper,we examine the role of the aspect ratio on the neutral penetration and poloidal distribution for fixed magnetic geometry and plasma profiles using SOLPS-ITER. We start from an H-mode discharge from MAST [9], with its aspect ratio of 1.4 and shift the magnetic equilibrium and vessel in major radius to generate a new SOLPS-ITER simul…
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UKAEA-CCFE-CP(25)132024
The end of tokamak operations at the Joint European Torus in December 2023 brought to a close the experimental life of an extraordinary fusion research facility.
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UKAEA-STEP-PR(25)252024
This paper discusses the importance of parallel and perpendicular magnetic field perturbations in gyrokinetic simulations of electromagnetic instabilities and turbulence at mid-radius in the burning plasma phase of the conceptual high-β, reactor-scale, tight-aspect- ratio tokamak STEP. Previous studies have revealed the presence of unstable hybrid…
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UKAEA-STEP-PR(25)242024
The UKAEA’s Spherical Tokamak for Energy Production (STEP) programme aims to demonstrate the ability of low aspect ratio tokamaks to generate net electricity from deuterium-tritium (DT) fusion. As STEP have selected REBCO coated conductor (CC) as the current carrier in most magnet systems, understanding how REBCO CC responds to the energetic p…
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UKAEA-CCFE-PR(24)2692024
The paper provides an assessment of the ion-cyclotron resonance heating (ICRH) system performance on JET since the year 2000. The vast amount of collected data offer an insight into the historical challenges and trends in the ICRH system performance encompassing the transition from carbon (JET-C) to beryllium (JET‑Be) first wall operations, th…
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UKAEA-CCFE-PR(24)2322024
The JET-ILW pure Tritium and Deuterium-Tritium (DTE2) experimental campaigns took place in 2021-2022. Tritium (T) and Deuterium-Tritium (D-T) operations present challenges not encountered in present day tokamaks [1]. This contribution focuses on Ion Cyclotron Resonance Heating (ICRH) operations in tritium and deuterium-tritium plasmas, starting …
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UKAEA-STEP-PR(24)132024
The purpose of the digital workstream is the shorten the pathway to delivering a working fusion pilot plant. As with any development pathway there are rate limiting steps in a programme, a fairly major challenge that is common across fusion concepts is the limited possibility of physical testing with conditions close to that of a first wall environ…
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UKAEA-CCFE-PR(25)2882023
Dedicated experiments were performed in JET DTE2 plasmas for obtaining α-particle bump-on-tail (BOT) distribution aiming at exciting Alfvén Eigenmodes (AEs) in baseline tokamak plasma scenario with safety factor q(0)~1. NBI-only heating with modulated power was used so that fusion-born α-particles were the only ions present in the MeV energy ran…
Showing 1 - 10 of 96 UKAEA Paper Results