A5102976383- Magnetic confinement fusion research
- Fusion materials and technologies
- Particle accelerators and beam dynamics
- Superconducting Materials and Applications
- Laser-Plasma Interactions and Diagnostics
- Ionosphere and magnetosphere dynamics
- Nuclear reactor physics and engineering
- Sulfur Compounds in Biology
- Metabolomics and Mass Spectrometry Studies
- Radio Astronomy Observations and Technology
- Antenna Design and Optimization
- Plasma Diagnostics and Applications
- Atomic and Molecular Physics
- Vitamin C and Antioxidants Research
- Radio Wave Propagation Studies
- Gyrotron and Vacuum Electronics Research
- Planetary Science and Exploration
- Astro and Planetary Science
United Kingdom Atomic Energy Authority
2022-2024
Culham Science Centre
2022-2024
Culham Centre for Fusion Energy
2022-2024
University of Wisconsin–Eau Claire
2024
Abstract STEP is a spherical tokamak prototype power plant that being designed to demonstrate net electric power. The design phase involves the exploitation of plasma models optimise fusion performance subject satisfying various physics and engineering constraints. A modelling workflow, including integrated core modelling, MHD stability analysis, SOL pedestal coil set free boundary equilibrium solvers, whole design, has been developed specify parameters develop viable scenarios. model JETTO...
Abstract We present an overview of results from a series L–H transition experiments undertaken at JET since the installation ITER-like-wall (JET-ILW), with beryllium wall tiles and tungsten divertor. Tritium, helium deuterium plasmas have been investigated. Initial in tritium show ohmic transitions low density power threshold for ( P LH ) is lower than ones densities, while we still lack contrasted data to provide scaling high densities. In there notable shift which minimum <?CDATA...
The UK’s Spherical Tokamak for Energy Production (STEP) reactor design program has recently taken the decision to use exclusively microwave-based heating and current drive (HCD) actuators its concepts. This is based on a detailed assessment considering all viable HCD concepts, covering grid plasma efficiency, physics applications, technology maturity, integration, maintenance, costs. Of two microwave techniques: Electron Cyclotron (EC) Bernstein Wave (EBW), EC was deemed lowest risk EBW...
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 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 Tritium and mixed deuterium-tritium experimental campaign on Joint European Torus (JET) device. High NBI power was high fusion yield alpha particle studies provide (D-T) fuelling core, it necessary operate JET systems both deuterium tritium. Further, pure tritium experiments performed T isotopic purity reduced...
GENRAY and CQL3D were used to estimate the Electron Bernstein Wave (EBW) current drive profiles normalised efficiency ζ CD (6) for several STEP reactor concepts with varying temperature, density, geometry magnetic field. > 1.0 was readily found ρ = 0.65 − 0.9 while 0.5 ≥ 0.5. Okhawa is be most efficient mechanism due high trapped fraction in STEP. Optimal 2 nd harmonic absorption ≤ 0.8 higher ν ⊥ at wave-particle resonance. 1 st required as there no access launch frequencies examined....
Abstract The power exhaust proves to be one of the most challenging and concept–defining aspects in design a commercial fusion plant, while magnetic coil system, capable supporting advanced solutions, emerges as main cost drivers. Consequently, much effort should dedicated optimisation robust global configuration, which integrates both plasma edge scenarios, ensuring engineering feasibility compatibility with available technology. Here we present multidisciplinary framework employed analyse,...
Lyman alpha transition line in exosphere deuterium implying enrichment factor ratio to earth surface
Neutral beam injection (NBI) is a very flexible auxiliary heating method for tokamak plasmas, capable of being efficiently coupled to various plasma configurations required in the tritium and deuterium–tritium experimental campaign (DTE2) be undertaken Joint European Torus (JET) device. In particular, experiments high fusion yield alpha particle studies require high-power NBI heating, maximum performance optimum fuel mixture control (D–T) it necessary operate JET systems both deuterium...
Abstract A fusion reactor based on the spherical tokamak is very likely to be completely non-inductive for majority of plasma ramp-up and steady-state phases, due limitations imposed central coil assemblies by compact design. Efficiency gains from solenoid-driven current cannot relied upon. It’s also critical that an electricity-producing plant maximises wall-plug efficiency its heating drive (HCD) system, this being one largest consumers recirculating power. It therefore essential HCD...