S. Smith

ORCID: 0000-0003-2319-0356
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About
Contact & Profiles
Research Areas
  • Magnetic confinement fusion research
  • Fusion materials and technologies
  • Superconducting Materials and Applications
  • Ionosphere and magnetosphere dynamics
  • Laser-Plasma Interactions and Diagnostics
  • Plasma Diagnostics and Applications
  • Nuclear reactor physics and engineering
  • Nuclear and radioactivity studies
  • Blind Source Separation Techniques
  • Radiation Effects and Dosimetry
  • Geophysical and Geoelectrical Methods
  • Non-Destructive Testing Techniques
  • Computational Fluid Dynamics and Aerodynamics
  • Advanced Sensor Technologies Research
  • Analytical Chemistry and Sensors
  • Satellite Communication Systems
  • Gas Sensing Nanomaterials and Sensors

University of York
2017-2025

General Atomics (United States)
2021-2024

Institut de Recherche sur la Fusion par Confinement Magnétique
2024

CEA Cadarache
2024

Culham Science Centre
2017-2024

Culham Centre for Fusion Energy
2024

United Kingdom Atomic Energy Authority
2021-2022

Oak Ridge National Laboratory
1997-2015

JOREK is a massively parallel fully implicit non-linear extended MHD code for realistic tokamak X-point plasmas. It has become widely used versatile studying large-scale plasma instabilities and their control developed in an international community. This article gives comprehensive overview of the physics models implemented, numerical methods applied solving equations studies performed with code. A dedicated section highlights some verification work done hierarchy different available...

10.1088/1741-4326/abf99f article EN cc-by Nuclear Fusion 2021-04-20

A disruption mitigation system (DMS) is under design for ITER to inject sufficient material deeply into the plasma rapid thermal shutdown and collisional suppression of any resulting runaway electrons. Progress on development both a shattered pellet injector (SPI) that produces large solid cryogenic pellets provide reliable deep penetration fast opening high flow rate gas valve massive injection (MGI) presented. Cryogenic deuterium neon up 25 mm in size have been formed accelerated with...

10.13182/fst14-926 article EN Fusion Science & Technology 2015-06-26

Future devices like JT-60SA, ITER and DEMO require quantitative predictions of pedestal density temperature levels, as well inter-ELM ELM divertor heat fluxes, in order to improve global confinement capabilities while preventing erosion/melting the planning future experiments. Such can be obtained from dedicated models EPED, non-linear MHD codes JOREK, for which systematic validation against current experiments is necessary. In this paper, we show progress JOREK code using JET simulations....

10.1088/1741-4326/aa6e2a article EN Nuclear Fusion 2017-04-20

Abstract Mega Ampere Spherical Tokamak (MAST) pedestal data has been analysed, where a database of 892 shots was obtained, using the upgraded MAST Thomson scattering (TS) diagnostic. Various edge localised mode (ELM) types are discussed, characteristics and trends pedestals shown. The from TS diagnostic confirms found in earlier analysis, previous systems. Using database, calculations bootstrap current obtained different analytical formulae (Sauter Redl), comparisons performed. system now...

10.1088/1361-6587/ac529b article EN cc-by Plasma Physics and Controlled Fusion 2022-02-07

Abstract A model for the pedestal density prediction based on neutral penetration combined with transport is presented. The tested against a database of JET-ILW Type I ELMy H-modes showing good agreement over wide range parameters both in standalone modelling (using experimental temperature profile) and full Europed that predicts pedestals simultaneously. further ASDEX Upgrade MAST-U are found to agree same as JET-ILW. experiment where isotope main ion varied D/T scan at constant gas rate...

10.1088/1741-4326/ad4b3e article EN cc-by Nuclear Fusion 2024-05-14

The high heat fluxes to the divertor during edge localised mode (ELM) instabilities have be reduced for a sustainable future tokamak reactor.A solution reduce could Super-X divertor, which will tested on MAST-U.ELM simulations MAST-U plasmas been obtained, using JOREK.A factor 10 decrease in peak flux outer target and almost 8 ELM energy fluence when comparing conventional configuration has found.A detached case, after roll-over parallel electron density flux, is used as starting point...

10.1088/1741-4326/ab826a article EN Nuclear Fusion 2020-03-24

The physics of the tokamak pedestal is still not fully understood, for example there no predictive model height and width. However, key in determining fusion power a given scenario. If we can improve our understanding reactor relevant pedestals will confidence designing potential plants. Work has been carried out as part collaboration on physics. We report some results detail here review wider work which be reported full elsewhere. First, attempt to use gyrokinetic-based calculation...

10.1088/1741-4326/ac12e9 article EN Nuclear Fusion 2021-07-09

A prototype 'smart' repeater that provides interoperability capabilities for radio communication systems in multi-agency and multi-user scenarios is being developed by the Oak Ridge National Laboratory. The smart functions as a deployable communications platform can be dynamically reconfigured to cross-link radios of participating federal, state, local government agencies. This interconnection capability improves coordination execution operations, including coordinated law enforcement...

10.1117/12.266741 article EN Proceedings of SPIE, the International Society for Optical Engineering/Proceedings of SPIE 1997-02-18
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