Abstract
Tokamaks are fusion machines that are under development to produce baseload power. Baseload power is power that is produced 24/7 and provides the base for powering the electric grid. The International Tokamak Experimental Reactor (ITER) is an international project that will produce net power from a Tokamak. Net power means the Tokamak produces more energy than it consumes. Consumption includes heating the plasma, controlling it, and powering all the auxiliary systems needed to maintain the plasma. It will allow researchers to study the physics of the Tokamak which will hopefully lead the way toward operational machines. A Tokamak is shown in Figure 6.1. The inner poloidal field coils act like a transformer to initiate a plasma current. The outer poloidal and toroidal coils maintain the plasma. The plasma current itself produces its own magnetic field and induces currents in the other coils.
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References
M.M.M. Al-Husari, B. Hendel, I.M. Jaimoukha, E.M. Kasenally, D.J.N. Limebeer, and A. Portone. Vertical stabilisation of Tokamak Plasmas. In Proceedings of the 30th Conference on Decision and Control, December 1992.
Barbara Cannas, Gabriele Murgia, A Fanni, Piergiorgio Sonato, Augusto Montisci, and M.K. Zedda. Dynamic Neural Networks for Prediction of Disruptions in Tokamaks. CEUR Workshop Proceedings, 284, 01 2007.
Wroblewski D. and et al. Tokamak disruption alarm based on neural network model of high-beta limit. Nuclear Fusion, 37(725), 11 1997.
Diederik P. Kingma and Jimmy Lei Ba. ADAM: A METHOD FOR STOCHASTIC OPTIMIZATION. 2015.
Y. Liang and JET EFDA Contributors. Overview of Edge Localized Modes Control in Tokamak Palsama. Technical Report Preprint of Paper for Fusion Science and Technology, JET-EFDA.
G.A. Ratta, J. Vega, A. Murari, the EUROfusion MST Team, and JET Contributors. AUG-JET cross-tokamak disruption predictor. In 2nd IAEA TM, 2017.
Paul A. Samuelson. Mathematics of speculative price. SIAM Review, 15(1):1–42, 1973.
R.O. Sayer, Y.K.M. Peng, J.C. Wesley, S.C. Jardin, CA General Atomics, San Diego, and NJ Princeton Univ. ITER disruption modeling using TSC (Tokamak Simulation Code). 11 1989.
Luigi. Scibile. Non-linear control of the plasma vertical position in a tokamak. PhD thesis, University of Oxford, 1997.
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© 2020 Michael Paluszek and Stephanie Thomas
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Paluszek, M., Thomas, S. (2020). Tokamak Disruption Detection. In: Practical MATLAB Deep Learning. Apress, Berkeley, CA. https://doi.org/10.1007/978-1-4842-5124-9_6
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DOI: https://doi.org/10.1007/978-1-4842-5124-9_6
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