Results 171 to 180 of about 1,622 (192)

Isotope dependence of transport in ST40 hot ion mode plasmas

Plasma Physics and Controlled Fusion, 2023
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 of 10 keV, surpassing their business milestone of 100 M ∘C (8.6 keV). The high temperature discharges were in the hot ion mode, with
S M Kaye, M Sertoli, P Buxton, A Dnestrovskii, S McNamara, M Romanelli, P Thomas   +6 more
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TriWaSp: a multi-faceted visible spectroscopy diagnostic on the ST40 tokamak

Journal of Instrumentation, 2023
Abstract We present a new state-of-the-art Triple Wavelength Spectrometer (TriWaSp), recently deployed on ST40, a high field low aspect ratio spherical tokamak. The TriWaSp has a range of possible applications due to its flexible design; the current configuration focuses on charge exchange recombination spectroscopy from carbon and neon ...
H.V. Willett, D. Osin, G. Naylor, J. Wood, B. Lomanowski, M. Sertoli   +5 more
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Design and commissioning of resistive foil bolometer diagnostics on the ST40 tokamak

Review of Scientific Instruments
Following successful campaigns on the compact high field spherical tokamak ST40, resistive gold foil bolometers have now been installed to measure the radiated power profile. Positioned on the midplane, two bolometer cameras offer perspectives of the horizontal and vertical planes, while the third camera, situated above the midplane, provides a ...
D. M. Harryman, C. Colgan, J. Lovell, M. Moscheni, G. Naylor, A. Rengle, M. Sertoli, A. Sladkomedova, R. Thwaites   +8 more
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On the design and role of passive stabilisation within the ST40 spherical tokamak

Plasma Physics and Controlled Fusion, 2018
Abstract The position of passive stabilisation has been optimised for the low aspect ratio tokamak ST40. We find that passive stabilisation is most effective when conductors are placed near the plasma’s x-point, and the combined effect of having both inboard and outboard passive stabilisation significantly reduces the vertical ...
P F Buxton, O Asunta, M P Gryaznevich, D Lockley, S McNamara, S Medvedev, E Ruiz de Villa Valdés, G Whitfield, J M Wood   +8 more
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ST40: Advancing the Physics Basis of Spherical Tokamak Reactors

2022
ST40 is a high field Spherical Tokamak, built and operated by Tokamak Energy, with R geo ≈0.4-0.5m, A≈1.6-1.9, κ<1.7, I p ≈0.4-0.8MA and B T ≈0.8-2.2T. Two co-injected hydrogen neutral beams deliver 0.8MW at 50kV and 0.7MW at 24kV. With deuterium the corresponding figures are 1.0MW/55kV and 0.8MW/24kV, respectively.
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Soft x-ray tomography on the high field spherical tokamak ST40

Review of Scientific Instruments
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 to expand the high field spherical tokamak physics basis by characterizing confinement and the fusion triple product.
C. Colgan, H. Bohlin, P. F. Buxton, D. M. Harryman, O. Jones, H. F. Lowe, G. Naylor, T. O’Gorman, T. Pyragius, M. Sertoli, A. Sladkomedova, S. Sridhar, R. Thwaites   +12 more
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Preparing for First Diverted Plasma Operation in the ST40 High-Field Spherical Tokamak [PDF]

, 2021
The ST40 tokamak [1], built and operated by Tokamak Energy, has recently been upgraded with upper and lower divertors to enable double null diverted operations with up to 1MA of plasma current and 2MW of neutral beam heating. ST40 is a high field spherical tokamak (BT=3T at R0=0.4m) with a goal to extend the high field spherical tokamak physics basis ...
Romanelli M, McNamara S, Buxton P, Asunta O, Varje J, Wood J, Marsden C, Bland J, Nemytov V, Thomas P, Gryaznevich M, Sertoli M, Vincent B, Sridhar S, Dnestrovsky A, Medvedev S, Drozdov V, Rubino G, Innocente P, Calabro' G, Scarpari M, Fanelli P, Giorgetti F, Lombroni R, Kaye S, Diallo A, Guttenfelder W, Barnes M, Zhang Y   +28 more
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Biological Shielding and Neutronics for the ST40 Tokamak

ICRS 14/RPSD 2022, 2022
J.O. Astbury, C. Wilson
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Measurement of divertor surface heat flux by infra-red thermographic inversion in ST40

Review of Scientific Instruments
Diagnostic tools for understanding the edge plasma behavior in fusion devices are essential. The main focus of the present work is to present the infra-red (IR) diagnostics installed on Tokamak Energy’s spherical tokamak (ST40) and the IR thermographic inversion tool, Functional Analysis of Heat Flux (FAHF).
M. Moscheni, E. Maartensson, M. Robinson, C. Marsden, A. Rengle, A. Scarabosio, P. Bunting, T. K. Gray, S. Janhunen, E. Vekshina, X. Zhang   +10 more
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Preparing for first diverted plasma operation in the ST40 high-field spherical tokamak

2022
sì
Romanelli, M., McNamara, S., Buxton, P., Asunta, O., Varje, J., Wood, J., Marsden, C., Bland, J., Nemytov, V., Thomas, P., Gryaznevich, M., Sertoli, M., Vincent, B., Sridhar, S., Dnestrovsky, A., Medvedev, S., Drozdov, V., Janhunen, S., Sinha, J., Bogaarts, T., Rubino, G., Innocenti, P., Calabrò, G., Scarpari, M., Fanelli, P., Giorgetti, F., Lombroni, R., Kaye, S., Diallo, A., Guttenfelder, W., Barnes, M., Zhang, Y.   +31 more
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