S. Davis

ORCID: 0000-0003-1795-2027
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About
Contact & Profiles
Research Areas
  • Superconducting Materials and Applications
  • Magnetic confinement fusion research
  • Particle accelerators and beam dynamics
  • Fusion materials and technologies
  • Particle Accelerators and Free-Electron Lasers
  • Spacecraft and Cryogenic Technologies
  • Physics of Superconductivity and Magnetism
  • Nuclear reactor physics and engineering
  • Reservoir Engineering and Simulation Methods
  • Nuclear Materials and Properties
  • Quantum and electron transport phenomena
  • Medical Imaging Techniques and Applications
  • Magnetic Properties and Applications
  • Surface and Thin Film Phenomena
  • Graphite, nuclear technology, radiation studies
  • Iron-based superconductors research
  • Nuclear Physics and Applications
  • Fiber-reinforced polymer composites
  • Advanced Thermoelectric Materials and Devices
  • Thermal Radiation and Cooling Technologies
  • Real-time simulation and control systems
  • Distributed and Parallel Computing Systems
  • Laser-Plasma Interactions and Diagnostics
  • Radiation Detection and Scintillator Technologies
  • Thermal properties of materials

Fusion for Energy
2013-2025

Ford Motor Company (United States)
2019

Max Planck Institute for Plasma Physics
2019

Universidad Complutense de Madrid
2017

Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas
2017

Northwestern University
2013

Max Planck Computing and Data Facility
2011

Culham Science Centre
2006-2010

Culham Centre for Fusion Energy
2006-2010

Carbon fibre composites offer considerable potential for mass reduction in automotive applications. However, raw material cost is one of the major factors that constraints its extensive use this market. Here we report a systematic study presents contributors by considering entire process chain carbon manufacturing. The sensitivity analysis revealed final Polyacrylonitrile (PAN) precursor and fibres were strongly influenced tow size. It was observed prompt decrease per kg sizes from 3k to...

10.1016/j.heliyon.2019.e02698 article EN cc-by-nc-nd Heliyon 2019-10-01

Abstract Construction of the JT-60SA tokamak was completed on schedule in March 2020. Manufacture and assembly all main components satisfied technical requirements, including dimensional accuracy functional performances. Development plasma heating systems diagnostics have also progressed, demonstration favourable electron cyclotron range frequency (ECRF) transmission at multiple frequencies achievement long sustainment a high-energy intense negative ion beam. operation control has been...

10.1088/1741-4326/ac10e7 article EN Nuclear Fusion 2021-07-02

The most distinctive feature of the superconducting magnet system for JT-60SA is optimized coil structure in terms space utilization as well highly accurate manufacturing, thus meeting requirements steady-state tokamak research: a conceptually new outer inter-coil separated from casing introduced to toroidal field coils realize their slender shape, allowing large-bore diagnostic ports detailed plasma measurements. A method minimize manufacturing error equilibrium-field has been established,...

10.1088/0029-5515/55/8/086001 article EN Nuclear Fusion 2015-06-30

The upgrade to JT-60SA tokamak (R = 3m, a 1.2m) was conducted within Europe-Japan collaboration agreement featuring the implementation of superconducting magnets. In 2021, magnet system commissioning initiated, undergoing cool-down and energization 18 Nb-Ti Toroidal Field (TF) coils (400 tonnes) up full nominal current. TF smoothly processed but it observed during current load higher outlet temperature increase TF02 coil versus others, indicating resistance in this circuit therefore possible...

10.1109/tasc.2024.3369596 article EN IEEE Transactions on Applied Superconductivity 2024-03-12

10.1109/tps.2024.3386174 article EN IEEE Transactions on Plasma Science 2024-05-16

JT-60SA, the largest tokamak that will operate before ITER, has been designed and built jointly by Japan Europe, is due to start operation in 2020.Its main missions are support ITER exploitation contribute demonstration fusion reactor machine scenario design.Peculiar properties of JT-60SA its capability produce long-pulse, high-β, highly shaped plasmas.The preparation Research Plan, plasma scenarios, producing physics results not only relevant future experiments, but often constitute...

10.1088/1361-6587/ab4771 article EN Plasma Physics and Controlled Fusion 2019-10-24

Abstract A large superconducting machine, JT-60SA has been constructed to provide major contributions the ITER program and DEMO design. For success of project fusion reactor, understanding development plasma controllability in relevant higher beta regimes are essential. focused on for scenario risk mitigation as well investigating regimes. This paper summarizes high research priorities strategy project. Recent works simulation studies prepare physics control experiments presented, such...

10.1088/1361-6587/ac57a0 article EN cc-by Plasma Physics and Controlled Fusion 2022-03-22

The superconducting tokamak fusion test device, JT-60SA, was constructed as the Satellite Tokamak project in Broader Approach Program between Japan and EU. During JT-60SA integrated commissioning tests of Nb-Ti equilibrium magnetic field coil EF1 high voltage (∼5 kV) test, power supply current surged suddenly stopped by overcurrent interlock supply. At same time, vacuum cryostat deteriorated, pressure magnet cooling loops increased. After system warmed up, visual inspection revealed that...

10.1109/tasc.2023.3347373 article EN IEEE Transactions on Applied Superconductivity 2023-12-27

The JT-60SA experimental device will be the world's largest superconducting tokamak when it is assembled in 2019 Naka, Japan (R = 3 m, a 1.2 m). It being constructed jointly by institutions EU and under Broader Approach agreement. Manufacturing of six NbTi equilibrium field (EF) coils, which have diameter up to 12 has been completed. So far, 13 18 toroidal (TF) each 7-m high 4.5-m wide, also manufactured tested at 4 K dedicated test facility France. first three four Nb3Sn central solenoid...

10.1109/tasc.2017.2768164 article EN IEEE Transactions on Applied Superconductivity 2017-11-09

The general design of the JT-60SA toroidal field system was defined in agreement with all participants project (CEA, ENEA, F4E), detailed issued by Voluntary Contributors. For French part including procurement 9 18 TF winding packs and their integration casings, an industrial contract signed mid-2011 Alstom (France). After on manufacturing drawings QA documentation, process giving guidelines for workshop organization definition required tooling. critical points were identified and, regarding...

10.1109/tasc.2013.2282571 article EN IEEE Transactions on Applied Superconductivity 2013-09-18

Monitoring of the intrinsic temperature and thermal management is discussed for carbon nanotube nano-circuits. The experimental results concerning fabricating testing a thermometer able to monitor on nanoscale are reported. We also suggest model which describes bi-metal multilayer system filter heat flow, based separating electron phonon components one from another. structure minimizes component while retaining electronic part. method allows improve overall performance nano-circuits due...

10.1063/1.4918667 article EN mit Journal of Applied Physics 2015-05-19

The JT-60SA is a fusion experiment designed to contribute the early realization of energy by providing support operation ITER; addressing key physics issues for ITER and DEMO; investigating how best optimize next devices that will be built after ITER. It combined project JA-EU Satellite Tokamak Program under Broader Approach (BA) JAEA's National Use, it in Naka, Japan, using infrastructure existing JT-60U experiment. superconducting magnet system consists Central Solenoid, six Equilibrium...

10.1109/tasc.2011.2178577 article EN IEEE Transactions on Applied Superconductivity 2011-12-21

The JT-60SA experiment will be the world's largest superconducting tokamak when it is assembled in Naka, Japan (R = 3 m, a 1.2 m). This paper describes approach taken to define appropriate manufacturing tolerances and metrology points for each toroidal field (TF) coil particular proposed procedure final assembly of TF magnet system.

10.1109/tasc.2011.2179693 article EN IEEE Transactions on Applied Superconductivity 2012-02-10
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