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Overview of recent results from the ST40 compact high-field spherical tokamak

Nuclear Fusion
ST40 is a compact, high-field ( $B_{\mathrm{T0}}\unicode{x2A7D} 2.1\,\,\,\textrm{T}$ ) spherical tokamak (ST) with a mission to expand the physics and technology basis for the ST route to commercial fusion.
S.A.M. McNamara, A. Alieva, M.S. Anastopoulos Tzanis, O. Asunta, J. Bland, H. Bohlin, P.F. Buxton, C. Colgan, A. Dnestrovskii, E. du Toit, M. Fontana, M. Gemmell, M.P. Gryaznevich, J. Hakosalo, M.R. Hardman, D. Harryman, D. Hoffman, M. Iliasova, S. Janhunen, F. Janky, J.B. Lister, H.F. Lowe, E. Maartensson, C. Marsden, S.Y. Medvedev, S.R. Mirfayzi, M. Moscheni, G. Naylor, V. Nemytov, J. Njau, T. O’Gorman, D. Osin, T. Pyragius, A. Rengle, M. Romanelli, C. Romero, M. Sertoli, V. Shevchenko, J. Sinha, A. Sladkomedova, S. Sridhar, J. Stirling, Y. Takase, P.R. Thomas, J. Varje, E. Vekshina, B. Vincent, H.V. Willett, J. Wood, E. Wooldridge, D. Zakhar, X. Zhang, D. Battaglia, N. Bertelli, P.J. Bonofiglo, L.F. Delgado-Aparicio, V.N. Duarte, N.N. Gorelenkov, M. de Haas, S.M. Kaye, R. Maingi, D. Mueller, M. Ono, M. Podesta, Y. Ren, S. Trieu, E. Delabie, T.K. Gray, B. Lomanowski, E.A. Unterberg, O. Marchuk, the ST40 Team   +71 more
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Ion and electron heating via magnetic reconnection during merging/compression plasma startup in ST40

Nuclear Fusion
Here, we report the latest results on the high-field application of a merging/compression (M/C) plasma startup in the ST40 spherical tokamak, using 96-channel 2D ion Doppler tomography and 30-channel Thomson scattering diagnostics installed over the past
H. Tanabe, R. Someya, T. Ahmadi, M.P. Gryaznevich, H.V. Willett, D. Osin, H.F. Lowe, H. Bohlin, T. O’Gorman, J. Wood, A. Rengle, S.A.M. McNamara, P.F. Buxton, O. Asunta, Y. Takase, J. Luo, S. Kobayashi, M. Inomoto, Y. Ono   +18 more
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SPECTROSCOPIC DIAGNOSTICS OF TOKAMAKS

Le Journal de Physique Colloques, 1988
AbstractImpurities being an important concern in tokamaks, spectroscopy plays a key role in their understanding. Techniques for the evaluation of concentrations, power losses and transport properties are surveyed, and a few developments are outlined.
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Tungsten melting and erosion under plasma heat load in tokamak discharges with disruptions

Nuclear Materials and Energy, 2017
Full tungsten poloidal and mushroom limiters were tested in series of experiments with disruptions in the T-10 tokamak. Significant melting, formation of small craters and erosion of the tungsten limiter have been observed after ∼400 discharges with ...
V.P. Budaev, Yu.V. Martynenko, S.A. Grashin, R.N. Giniyatulin, I.I. Arkhipov, A.V. Karpov, P.V. Savrukhin, E.A. Shestakov, R.Yu. Solomatin, L.B. Begrambekov, N.E. Belova, S.D. Fedorovich, L.N. Khimchenko, V.M. Safronov   +13 more
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Dust remobilization from rough planar surfaces in tokamak steady-state plasmas

Nuclear Materials and Energy, 2018
The ability of tungsten (W) dust to be remobilized from rough tokamak plasma-facing surfaces is investigated in this study. Atomic Force Microscopy is used to evaluate the adhesion force distribution between W spheroids of ∼1−10 µm radius and a rough W ...
A. Autricque, S. Peillon, F. Gensdarmes, M. Sow, N. Fedorczak, H. Roche, O. Pluchery, C. Grisolia   +7 more
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Cross-tokamak disruption prediction based on domain adaptation

Nuclear Fusion
The high acquisition cost and the significant demand for disruptive discharges for data-driven disruption prediction models in future tokamaks pose an inherent contradiction in disruption prediction research.
Chengshuo Shen, Wei Zheng, Bihao Guo, Yonghua Ding, Dalong Chen, Xinkun Ai, Fengming Xue, Yu Zhong, Nengchao Wang, Biao Shen, Binjia Xiao, Zhongyong Chen, Yuan Pan, J-TEXT Team   +13 more
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Optimization and Process Modeling of Plasma Gasifier via Aspen Plus and Surrogate Model for Treatment of Municipal Solid Waste

ChemEngineering
Plasma gasification is a sustainable and advanced technology for the safe and efficient treatment of municipal solid waste (MSW). In this process, a plasma torch serves as the primary heating source to convert MSW into syngas and inert vitrified slag ...
Hamza Ahmad, Ahmad Ali, Kashif Rashid, Ahmed Omer, Riaz Khan, Wajahat Waheed Kazmi, Faysal M. Al-Khulaifi   +6 more
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Helicon Wave Auxiliary Current Drive under D-T Plasma Operation Mode on HL-3 Tokamak Device

Yuanzineng kexue jishu
The D-T plasma discharge is a critical operational mode for reactor-grade Tokamak devices. The helicon wave current drive on HL-3 Tokamak device was studied in the paper.
WANG Sen1, ZI Daozheng1, CHENG Zehou1, LI Xinxia1, 2,
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Tritium production and processing systems for ST-E1

Nuclear Fusion
An integrated tritium fuel-cycle architecture has been developed for ST-E1, a low-aspect-ratio, high-power fusion power plant. The approach couples a helium-cooled liquid-lithium breeder blanket with a dedicated circulation loop providing tritium ...
E. Yildirim, J. Naish, J. Trueba, S. Levine, A. Kumar, V.B. Gohani, M.K.E. Mohamed, A. Vorobev, L. Yang, P.C. Simon, A. Somers, C. Malone, H. Flynn, P. Rowell, T. Stahl, G.K. Larson, R. Barnett, L.R. Baylor, T.E. Gebhart, N. Adhikari   +19 more
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Numerical Studies and Simulation of the Lower Hybrid Waves Current Drive by using Fokker – Planck Equation in NSST and HT-7 Tokamaks [PDF]

Journal of Sciences, Islamic Republic of Iran, 2014
Recent experiments on the spherical tokamak have discovered the conditions to create a powerful plasma and ensure easy shaping and amplification of stability, high bootstrap current and confinement energy.
A.A. Molavi Choobini
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