Page 462 - Fundamentals of Magnetic Thermonuclear Reactor Design
P. 462

Index     439


               parameters, 46                  feedback control algorithms, 247
               poloidal field coils, 49        linear model derivation, 251
               TF and correction coils, 45     magnet configuration, 249
               toroidal and poloidal magnetic field coils, 45  magnetic flux surfaces, 248
               toroidal field coils, 47        matrixes of linear equations (MLE), 251
             Main circuit breaker (MCB), 331, 332  non-linear modelling, 258
             Make switch (MS), 329             optimisation design, 249
             Matrixes of linear equations (MLE), 251  parametric and model uncertainties, 249
             Maxwell stress tensor, 79         plasma column position and shape
             Mechanical loads, vacuum vessel, 369  reconstruction
               coolant pressure, 370             current filament method, 276
               EMLs, 369                         harmonic method, 276
               thermomechanical loads, 370       local approximation method, 276
             Mirror-stellarator hybrid, 11       reconstruction methods, 276
             Motor generators (MG), 325          simple-layer potential method, 276
               advantages, 326                 plasma transport model, start-up
               kinetic energy, 326                 phase, 268
                                               stationary toroidal field, 248
                                               tokamak electromagnetic processes, 266
             N                                Plasma heating systems
             Natural lithium, 292              adiabatic compression, 282
             Neutral beam (NB) injection, 282  current drive methods, 289
             Next-Generation (Prospective) Fusion Blanket,   electron cyclotron resonance heating, 286
                  308                          fast atom injection, 282
               ARIES-AT (United States), 309   ion cyclotron resonance heating, 288
               EVOLVE (United States), 309     lower hybrid resonance heating, 289
               FFHR-2 (Japan), 309             neutral beam (NB) injection, 282
               HCPB (Europe), 309              ohmic heating, 282
               SSTR-2 (Japan), 306             plasma stability, 281
               TAURO (Europe), 309            Poloidal field (PFC), 354, 368
               V/Li/He (United States), 309    central solenoid coils
               W/Li/He (United States, 309       discharge current pulses, 333
             Non-linear modelling, 258           electrical load of, 333
                                                 energy-demanding systems, 334
             O                                   energy storage phase, 336
             Outboard blanket (OB), 296, 299     low power and energy consumption, 333
                                                 magnetic flux, 334
                                                 preliminary energy storage, 336
             P                                   T-3 CS power supply circuit, 334
             Pinches, 11                         T-10 CS power supply circuit, 334, 335
             Pirobreaker (PB), 331, 347          T-15 PF coils, 336
             Plasma control system             ITER
               analytical synthesis and control system   circuit scheme and equipment, 342
                  optimisation                   discharge resistors, 340
                basic features, 260              FOS, 340
                problem generalisation, 261      grounding, 341, 342
               design methodology, 249           PF1 and PF6 coils, 337
               electro-physical and electro-technical   PF2–PF5 coils, 337, 341, 342
                  operations, 248                poloidal magnetic fields, 337
               engineering problems, 248         quasisymmetrical current distribution, 342
               error field correction            switching network unit, 338, 339
                field perturbation harmonic analysis, 271  TCB, 339
                ITER correction coils, 273       thyristor converter, 338
                plasma processes, 270          plasma equilibrium control coils, 336
   457   458   459   460   461   462   463   464   465   466   467