A5051174917- Magnetic confinement fusion research
- Fusion materials and technologies
- Laser-Plasma Interactions and Diagnostics
- Superconducting Materials and Applications
- Particle accelerators and beam dynamics
- Nuclear reactor physics and engineering
- Plasma Diagnostics and Applications
Culham Science Centre
2022-2024
Culham Centre for Fusion Energy
2022-2024
United Kingdom Atomic Energy Authority
2024
École Polytechnique Fédérale de Lausanne
2024
Oak Ridge National Laboratory
2022
Abstract The recent deuterium–tritium campaign in JET-ILW (DTE2) has provided a unique opportunity to study the isotope dependence of L-H power threshold an ITER-like wall environment (Be and W divertor). Here we present results from dedicated transition experiments at JET-ILW, documenting tritium plasmas, comparing them with matching deuterium hydrogen datasets. From earlier it is known that as plasma isotopic composition changes deuterium, through varying deuterium/hydrogen concentrations,...
Abstract This paper reports the first experiment carried out in deuterium–tritium addressing integration of a radiative divertor for heat-load control with good confinement. Neon seeding was time D–T plasma as part second campaign JET its Be/W wall environment. The technical difficulties linked to re-ionisation heat load are reported T and D–T. compares impact neon on plasmas their D counterpart detachment, localisation radiation, scrape-off profiles, pedestal structure, edge localised modes global
Abstract Building on prior analysis of ASDEX Upgrade (AUG) experiments (Henderson et al 2023 Nucl. Fusion 63 086024), this study compares simple analytical formula predictions for divertor detachment onset and reattachment timescales in JET experiments. Detachment primarily scales with neutral pressure, impurity concentration, power directed to the targets, machine size, integral perpendicular decay length. experiments, focusing seeding mixtures Ne Ar, align predictions. Radiation...
We present here the results of spectroscopic analysis high-resolution visible spectra beryllium hydride and its isotopologues (BeH, BeD, BeT), produced during plasma–surface interactions limiter divertor JET-ILW (ITER-like Wall) pulses. The production, being an important part wall erosion via chemical-assisted physical sputtering, shows dependence on plasma conditions, also isotope content plasma. This work that this is true for molecular energy distributions, parameterized by rotational...
Measurements of the ion currents to and plasma conditions at low-field side (LFS) divertor target plate in low-confinement mode plasmas JET ITER-like wall materials configuration show that core density required detach LFS is independent hydrogenic species protium, deuterium tritium, a 40 %/60 % deuterium–tritium mixture. This observation applies with strike line connected horizontal part chosen because its superior diagnostic coverage. The finding operational status cryogenic pump. electron...
Abstract The experimental and theoretical analysis were focused on experiments conducted to assess the effect of plasma isotopes, protium (H), deuterium (D), tritium (T) ion cyclotron resonance heating (ICRH) related wall interactions. Comparison L-mode discharges with N = 1 3 He H minority ICRH scenarios done for different isotopes. For selected pulses, behaviour high-Z, mid-Z low-Z intrinsic impurity radiated power was investigated based data from VUV, visible spectroscopy, bolometry...
For JET L-mode plasmas in low-recycling conditions (electron temperature at the outer strike point, Te,ot≳30eV), SOLPS-ITER simulations agree within error bars for experimental profiles low-field side (LFS) divertor target. The peak Balmer-α (Dα) emission LFS agrees of KS3 filterscope diagnostic, but is approximately 30% lower than value KT1 spectrometer. Simulations have been performed with fluid, kinetic, and hybrid models neutrals. large fluid-kinetic discrepancies more a factor 2 are...
Langmuir probe measurements in neutral beam injection (NBI) heated, low-confinement mode plasmas JET ITER-like wall showed that the current to divertor targets, Idiv, helium (He) was up 70% lower on low-field side (LFS) than otherwise identical deuterium (D) plasmas. The edge plasma density at which rollover of Idiv occurred i.e. onset detachment, 10% higher He both LFS and high-field (HFS). increases by 25% for when NBI power 1MW 5MW. total radiated similar D densities below rollover. At...
Abstract The behaviour of impurities in fusion plasmas is crucial importance for achieving sustained reactions, and understanding similarities differences between Deuterium (D) Tritium (T) needed to assess potential changes from DD DT ITER future reactors. first dimensionless dimensional isotope identity experiments L-mode were conducted at the JET W/Be wall. In approach, discharges with matched ρ ∗, ν β n , q T e / i compared emphasize direct effects, while approach engineering parameters...