A5021286200- Magnetic confinement fusion research
- Superconducting Materials and Applications
- Fusion materials and technologies
- Particle accelerators and beam dynamics
- Nuclear reactor physics and engineering
- Laser-Plasma Interactions and Diagnostics
- Nuclear Physics and Applications
- Ionosphere and magnetosphere dynamics
- International Science and Diplomacy
- Aerosol Filtration and Electrostatic Precipitation
- Solar and Space Plasma Dynamics
- Non-Destructive Testing Techniques
- Frequency Control in Power Systems
- Korean Peninsula Historical and Political Studies
- Plasma Diagnostics and Applications
- Magnetic Properties and Applications
- Power System Optimization and Stability
- Neural Networks and Applications
Tokamak Energy (United Kingdom)
2015-2025
Culham Science Centre
2014-2017
University of York
2013-2015
Abstract A fusion nuclear science facility (FNSF) could play an important role in the development of energy by providing environment needed to develop materials and components. The spherical torus/tokamak (ST) is a leading candidate for FNSF due its potentially high neutron wall loading modular configuration. key consideration choice configuration range achievable missions as function device size. Possible include: fluence, demonstrating tritium self-sufficiency, electrical self-sufficiency....
Tokamak Energy Ltd, UK, is developing spherical tokamaks using high temperature superconductor magnets as a possible route to fusion power relatively small devices. We present an overview of the development programme including details enabling technologies, key modelling methods and results, remaining challenges on path compact fusion.
Abstract Ion temperatures of over 100 million degrees Kelvin (8.6 keV) have been produced in the ST40 compact high-field spherical tokamak (ST). excess 5 keV not previously reached any ST and only obtained much larger devices with substantially more plasma heating power. The corresponding fusion triple product is calculated to be <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" overflow="scroll"> <mml:mrow> <mml:msub> <mml:mi>n</mml:mi> <mml:mi>i</mml:mi> <mml:mn>0</mml:mn>...
It is generally accepted that the route to fusion power involves large devices of ITER scale or larger. However, we show, contrary expectations, for steady state tokamaks operating at fixed fractions density and beta limits, gain, Qfus, depends mainly on absolute level energy confinement, only weakly device size. Our investigations are carried out using a system code also by analytical means. Further, show two qualitatively different global scalings have been developed fit data contained in...
Abstract ST40 is a compact, high-field ( <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" overflow="scroll"> <mml:mrow> <mml:msub> <mml:mi>B</mml:mi> <mml:mi mathvariant="normal">T</mml:mi> <mml:mn>0</mml:mn> </mml:mrow> </mml:msub> <mml:mtext>⩽</mml:mtext> <mml:mn>2.1</mml:mn> <mml:mstyle scriptlevel="0"/> <mml:mtext>T</mml:mtext> </mml:math> ) spherical tokamak (ST) with mission to expand the physics and technology basis for ST route commercial fusion. The research programme covers...
The ability to model the interplay between core and edge of tokamak plasmas is crucial designing both plasma operating scenario a fusion pilot plant design itself. Scrape-off-layer (SOL) models that are tailored integrated modeling need have fast turn-around time minimal computational burden enable wide parameter-space coverage for scoping. SOL 0-D Box reduced based on global power particle balance captures essential physics transport with little cost. usage in core-edge coupled simulations...
Numerical studies have been made to improve the performance of central column a superconducting spherical tokamak fusion pilot plant. The assumed neutron shield includes concentric layers tungsten carbide and water. relative thickness water was varied minimum power deposition found at about 17% It advantageous an approximately 1.7 times thicker layer next core similarly thinner plasma. use boride instead shown make improvement especially if placed close core, inner alone reducing by 29%....
A new spherical tokamak, the SMall Aspect Ratio Tokamak (SMART), is currently being designed at University of Seville. The goal machine to achieve a toroidal field 1 T, plasma current 500 kA and pulse length ms for with major radius 0.4 m minor 0.25 m. This contribution presents design coils power supplies machine. foresees central solenoid, 12 8 poloidal coils. Taking waveforms these set as starting point, each them has been withstand Joule heating during tokamak operation time. An...
A key challenge in designing a fusion power plant is to manage the heat deposition into central core containing superconducting toroidal field coils. Spherical tokamaks have limited space for shielding from fast neutrons produced by and resulting gamma rays. This paper reports series of three-dimensional computations using Monte Carlo N-particle code calculate core. For given power, this considered as function plasma major radius R0, rsc shield thickness d. Computations over ranges 0.6 m ⩽...
Experiments on NSTX and MAST have shown the thermal energy confinement time in spherical tokmaks (STs), , to a stronger toroidal field weaker plasma current dependence than conventional large aspect ratio tokamaks. These scalings were derived for single machines both of which are similarly sized, consequently scaling laws do not include size dependence, so cannot be used extrapolate performance future STs. Using physics-based dimensional arguments we extend scaling. We also resolve...
Stambaugh developed the Peng-Hicks concept of a fusion reactor based on solid copper center-post spherical tokamak (ST). Using promising results from START experiment, they produced vision for path to power. This had two elements such as ability produce high gain an ST and equal importance, demonstrate this in small (and therefore relatively low cost) pilot plant device. In paper, we review various attempts pursue vision, try elucidate reason why success has not yet been achieved. However,...
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...
The SMall Aspect Ratio Tokamak (SMART) device is a new compact (plasma major radius Rgeo≥0.40 m, minor a≥0.20 aspect ratio A≥1.7) spherical tokamak, currently in development at the University of Seville. SMART has been designed to achieve magnetic field plasma center up Bϕ=1.0 T with currents Ip=500 kA and pulse length τft=500 ms. A wide range shaping configurations are envisaged, including triangularities between −0.50≤δ≤0.50 elongations κ≤2.25. Control achieved through four axially...
The dithering H-mode phase, characterized by oscillations, is generally observed at input power values close to the L-H transition threshold and low plasma collisionalities (low electron density and/or high temperature). Measurements characterize phase are presented for aspect ratio, magnetic field tokamak, ST40. oscillation frequency between 400 800 Hz demonstrates an inverse relationship with core density. Dithering H-modes documented across a nonlinear, low-density operational space,...
Tokamak Energy Ltd. is developing compact fusion power plants based on two promising technologies, Spherical Tokamaks (STs) and High Temperature Superconductors (HTS), with the aim to build a first demonstrative plant by 2030′s. On its path power, presently operating ST40, new generation ST that currently highest field device of kind. In near future, an important ST40 upgrade planned foresees manufacturing installation vacuum chamber, called IVC2. This will allow exploitation maximum...
As part of its roadmap to developing commercial fusion plants, Tokamak Energy Ltd. operates the high field spherical tokamak ST40. Studies on this device will help expand physics basis by characterizing confinement and triple product. In support this, bolometers broadband x-ray sensitive diodes can provide information key energy loss mechanisms plasma. These include core magnetohydrodynamic activity that deteriorates confinement, such as sawtooth crashes be used characterize relaxations in...
Abstract Linear and nonlinear perturbative analyses of low-frequency instabilities are presented for ST40 spherical torus high field plasmas, with simultaneous neutral beam heating due to two tangential sources at 25 keV 55 keV. Initial plasma profiles on which the TRANSP NUBEAM codes were based obtained using an integrated analysis several diagnostics including line-of-sight volume average measurements, as well limited profile information from a charge-exchange-recombination spectrometer....
Abstract The ST40 compact, high-field spherical tokamak, operating at 2.1 T and with 1.8 MW of neutral beam heating, achieved central carbon impurity ion temperatures in excess 10 keV, surpassing their business milestone 100 M ∘ C (8.6 keV). high temperature discharges were the hot mode, <?CDATA $T_i \gg T_e$?> <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" overflow="scroll"> <mml:msub> <mml:mi>T</mml:mi> <mml:mi>i</mml:mi> </mml:msub> <mml:mo>≫</mml:mo> <mml:mi>e</mml:mi>...
AbstractThe realization of power from Magnetic Confinement Fusion is presently following a plan that will span several decades. The mainstream route via ITER, combined with, or followed by, materials development on Neutron Science Facility, then DEMO reactor, which, as visualised, considerably larger than ITER. We consider smaller-scale alternatives and developments which may make more rapid progress towards the much needed goal economic, safe, clean fusion power, but still based tokamak.
This paper presents results of studies fast particles (ions and alpha particles) in a steady-state compact fusion neutron source (CFNS) spherical tokamak (ST) reactor with Monte-Carlo Fokker–Planck codes. Full-orbit simulations particle physics indicate that high field ST can be optimized for energy production by reduction the necessary (for containment) plasma current compared predictions made using simple analytic expressions, or guiding centre approximation numerical code. Alpha losses...
The paper aims to define the structural behavior of ST40 Inner Vacuum Chamber (IVC2) under action electromagnetic loads from a previously analysed plasma disruption scenario, namely an Upward Vertical Displacement Event (UVDE) scenario. This spherical tokamak is owned by Tokamak Energy Ltd, and it highest field device its kind. considered are obtained previous analysis [1] interpolated on model. Indeed, study represents second final part IVC2 characterization. maximum load due eddy current...
The position of passive stabilisation has been optimised for the low aspect ratio tokamak ST40. We find that is most effective when conductors are placed near plasma's x-point, and combined effect having both inboard outboard significantly reduces vertical instability growth rate. rate can be further decreased by cooling down to 80 K. Two concepts considered, plates coils, relative advantages disadvantages each discussed. Both involve connecting upper lower in an 'anti-symmetric' manner,...