A5025686733- Magnetic confinement fusion research
- Fusion materials and technologies
- Nuclear reactor physics and engineering
- Superconducting Materials and Applications
- Particle accelerators and beam dynamics
- Fluid Dynamics and Turbulent Flows
- Ionosphere and magnetosphere dynamics
- Laser-Plasma Interactions and Diagnostics
- Gas Dynamics and Kinetic Theory
- Model Reduction and Neural Networks
- Nuclear Materials and Properties
United Kingdom Atomic Energy Authority
2022-2024
Culham Centre for Fusion Energy
2022-2024
Culham Science Centre
2022-2023
Abstract The quasi-continuous exhaust (QCE) regime is a that naturally type-I ELM-free. It combines the high density at plasma edge needed for power with normalised energy confinement typical H-mode operation. In QCE large-scale ELMs are avoided and high-frequent, low-amplitude filaments present leading to name-giving transport of particles energy.
This contribution reports first time was successfully achieved in JET metal wall. More so, it demonstrated recent deuterium-tritium...
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 Deuterium (D) and beryllium (Be) fluxes are obtained in JET Low-confinement (L-mode) plasmas at the outer limiters of first wall using calibrated visible cameras. They inferred from measured radiances spectroscopic S/XB method. From fluxes, effective gross erosion yield Yeff limiter surface is estimated. After discussing uncertainties proposed methodology, we show dependence deduced particle recent L-mode on: separatrix-limiter clearance, magnetic field plasma current, NBI ICR...
Abstract Divertor power load is a major challenge towards burning plasma in next-step tokamak. Here, the first results of divertor characterisation tritium plasmas type-I ELMy H-mode, obtained JET deuterium-tritium campaign (DTE2) performed 2021, are presented. It demonstrated that both, transient loads due to ELMs as well fall-off length, do not exhibit an explicit ion mass dependence, with remarkably similar values and deuterium references. This gives improved credence published scaling...
Abstract The isotope effect, hydrogen (H) versus deuterium (D), on the gross beryllium (Be) erosion yield has been measured in ohmic limiter plasmas JET tokamak by spectroscopic means. A simplified method to extract effective sputtering from quotient of radiances D α or γ and Be II lines at 527 nm was applied. clear effect found, being about a factor 2 larger compared H whole explored plasma density range. This is agreement with physical data obtained + ion beams also material surface...
Power loading from plasma in the scrape-off layer limits lifetime of plasma-facing components tokamak-based power plants. The Mega Ampere Spherical Tokamak Upgrade [W. Morris et al., IEEE Trans. Plasma Sci. 46(5), 1217–1226 (2018)] (MAST-U) features four divertor strike points (SP) owing to its up-down symmetry. This paper introduces five-camera infrared thermography system, covering all SPs and their mode operation on MAST-U. system employs both medium long wavelength cameras, offering high...