E. Litherland-Smith

ORCID: 0009-0000-0587-2930
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About
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Research Areas
  • Magnetic confinement fusion research
  • Fusion materials and technologies
  • Superconducting Materials and Applications
  • Nuclear reactor physics and engineering
  • Fault Detection and Control Systems
  • Nuclear Physics and Applications
  • Nuclear Materials and Properties
  • Anomaly Detection Techniques and Applications
  • Ionosphere and magnetosphere dynamics
  • Atomic and Subatomic Physics Research

United Kingdom Atomic Energy Authority
2022-2024

Culham Centre for Fusion Energy
2024

Culham Science Centre
2022-2024

Abstract This paper presents a study on the dependence of ion temperature stiffness plasma main isotope mass in JET ITER-like wall and C discharges. To this aim, database H, D T shots is analyzed, including new dedicated shots, comparing experiments with lower higher power injected by NBI system. In order to characterize turbulence mass, three these discharges (two one D) same external heating scheme are studied detail interpreted gyrokinetic linear nonlinear simulations. The analysis...

10.1088/1741-4326/adab04 article EN cc-by Nuclear Fusion 2025-01-16

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

10.1088/1741-4326/ad69a2 article EN cc-by Nuclear Fusion 2024-07-31

Abstract JET returned to deuterium-tritium operations in 2023 (DTE3 campaign), approximately two years after DTE2. DTE3 was designed as an extension of JET's 2022-2023 deuterium campaigns, which focused on developing scenarios for ITER and DEMO, integrating in-depth physics understanding control schemes. These were evaluated with mixed D-T fuel, using the only remaining tritium-capable tokamak until its closure 2023. A core-edge-SOL integrated H-mode scenario developed tested D-T, showing...

10.1088/1361-6587/adbd75 article EN Plasma Physics and Controlled Fusion 2025-03-06

Abstract Like most magnetic confined fusion experiments, the ST40 tokamak started off with a small subset of diagnostics and gradually increased diagnostic set to include more complex comprehensive systems. To make each operational phase, forward models various are used developed aid design, provide consistency-checks during commissioning, test analysis methods, build workflows constrain high-level parameters inform interpretation, theory modelling. For new workflows, minimum-viable-products...

10.1088/1361-6587/ad668f article EN cc-by Plasma Physics and Controlled Fusion 2024-08-02

Magnetically confined plasma experiments generate a wealth of spectroscopic data. The first step toward extracting physical parameters is to fit spectral model the often complex spectra. CXSFIT (Charge eXchange Spectroscopy FITting) fitting code was originally developed for charge exchange spectra on JET from late 1980s onward and has been further over decades keep up with needs users. primary use efficiently large number many constrained Gaussian lines which can be coupled in user-friendly...

10.1063/5.0219427 article EN Review of Scientific Instruments 2024-08-01
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