A5045470535- Magnetic confinement fusion research
- Fusion materials and technologies
- Superconducting Materials and Applications
- Nuclear reactor physics and engineering
- Nuclear Materials and Properties
- Laser-Plasma Interactions and Diagnostics
- Aerosol Filtration and Electrostatic Precipitation
- Non-Destructive Testing Techniques
- Microstructure and Mechanical Properties of Steels
- Advanced materials and composites
- High-Energy Particle Collisions Research
- Electromagnetic Launch and Propulsion Technology
Tokamak Energy (United Kingdom)
2021-2025
Royal Military Academy
2020
Culham Science Centre
2016-2019
Culham Centre for Fusion Energy
2016-2018
United Kingdom Atomic Energy Authority
2017
The key remaining physics design issue for the ITER tungsten (W) divertor is question of monoblock (MB) front surface shaping in high heat flux target areas actively cooled targets. Engineering tolerance specifications impose a challenging maximum radial step between toroidally adjacent MBs 0.3 mm. Assuming optical projection parallel loads, magnetic shadowing these edges required if quasi-steady state melting to be avoided under certain conditions during burning plasma operation and...
Diagnostic tools for understanding the edge plasma behavior in fusion devices are essential. The main focus of present work is to infra-red (IR) diagnostics installed on Tokamak Energy’s spherical tokamak (ST40) and IR thermographic inversion tool, Functional Analysis Heat Flux (FAHF). FAHF designed multi-2D inversions within divertor tiles using finite difference method an explicit time stepping scheme. ST40’s re-entrant endoscope allows acquisition data with highest available effective...
Digital twin techniques enhance traditional engineering analysis workflows of existing systems when a realistic evaluation component under complex operating conditions is required. During preparation, commissioning and phases, components can be virtually tested by using validated numerical models, operational expertise, experimental databases. Three complementary applications have been developed this approach. The models used for the divertor tiles are based on continuum mechanics...
Melting is one of the major risks associated with tungsten (W) plasma-facing components (PFCs) in tokamaks like JET or ITER. These are designed such that leading edges and hence excessive plasma heat loads deposited at near normal incidence avoided. Due to high stored energies ITER discharges, shallow surface melting can occur under insufficiently mitigated disruption so-called edge localised modes—power load transients. A dedicated program was carried out study physics consequences W...
In this paper we discuss results from the study of energy balance in JET based on calculated heating energies, radiated bolometry and tile calorimetry. Recent data enables us to be more confident numbers used exclude certain possibilities but overall imbalance which typically amounts 25% total input remains unexplained. This shows that caution is required interpreting fractional powers are commonly measure effectiveness impurity seeded scenarios at reducing divertor heat load.
Parallel heat flux calculations at the JET divertor have been based on assumption that all incoming is due to projection of parallel magnetic line, , plus a constant background. This simplification led inconsistencies during analysis series dedicated tungsten melting experiments performed in 2013, for which infrared (IR) thermography surface measurements could not be recreated through simulations unless was reduced by 80% L-mode and 60% H-mode. We give an explanation these differences using...
Tungsten (W) melting is a major concern for next step fusion devices.Two ELM induced tungsten experiments have been performed in JET by introducing two special target plate lamellae designed to receive excessively high transient power loads.The first experiment was 2013 using lamella with sharp leading edge gradually varying from h = 0.25 mm 2.5 order maximise the temperature rise exposure full parallel heat flux.ELM-induced has successively achieved allowing investigation of melt...
Modelling the structural effects of vertical displacement events (VDEs) on plasma facing components is critical for component integrity but can be both computationally intensive and time consuming. In early-stage design, a simple analysis method useful to compare concepts. This paper describes methods that uses commercially available ANSYS software obtain estimations forces torques arising from VDE induced currents halo currents. The will used inform design in-vessel assemblies Tokamak...