Page 461 - Fundamentals of Magnetic Thermonuclear Reactor Design
P. 461

438    Index


            LLCB blanket (India), 305           maximum allowable stress, TFC, 363
            Lower hybrid resonance heating, 289  MS mechanical behaviour, 360
            Low-temperature radiation embrittlement   off-normal current combinations in
                 (LTRE), 393, 394                 windings, reaction to, 364
                                                stress analysis, 361
                                                superconducting magnet systems, thermal
            M                                     mechanics of, 366
            Magnetic fusion reactors (MFR), 122  tokamaks, codes and standards for, 383
              basic correlations               tokamak superconducting magnet, load
               ITER, 3                            schemes
               Joule heating, 3                 design and computation, general
               magnetohydrodynamic approximation, 4  algorithm for, 354
              composite windings, computations for   poloidal field coils and central
               global finite-element model, 356   solenoid, 354
               ITER PF1 coil composite winding, 357  toroidal field coils, 353
               KSTAR tokamak CS, 361           tritium, 1
               maximum allowable jacket stress, 358, 359  Magnetic mirrors, 10
               periodicity cell, local finite-element   Magnetic plasma confinement
                 method, 356, 357              force loads, on tokamak components, 25
               PF1 coil, averaged toroidal stresses in,   hybrid systems, 11
                 357, 358                      in-chamber conditions, 24
               PF1 coil conductor jacket, toroidal stress   magnetic mirrors, 10
                 in, 359                       magnet system, 23
               ponderomotive forces, 357       pinches, 11
               superconducting composite windings, 356  plasma equilibrium, 9
               typical stress fields, 360      plasma heating, 9
              copper radiation damageability, estimates   plasma stability, 9
                 of, 397                       radiation shielding, 27
              deuterium and protium, 1         spheromaks, 12
              fusion reactor safety. See Fusion reactor   stellarators, 9
                 safety                        tokamak functional assembly, 8
              ITER toroidal field coil, physical simulation   Magneto-elastic stability
                 of, 382                       of ITER poloidal field coil system
              magneto-elastic stability         CS parameters, 376
               ITER poloidal field coil system, 374  elastic forces’ overall potential, 377
               poloidal field coil, 379         elastic mechanical supports, 377
               problem statement, 366           electromagnetic forces, potential of, 377
               toroidal and poloidal field systems, 367  force acting on, 376
              physical basis, 2                 magnetic stiffness matrix, 376, 379
              radiation materials, 399          magnetomechanical interaction
              mechanical issues, 352              potential, 376
              mechanical strength and thermal stress   mutual magnetic stiffness,
                 analysis, 352                    estimation of, 375
              stellarator structural analysis, 372  parameters of, 378
              strength and stiffness analysis, vacuum   safety factor, 378
                 vessel                         stability characteristics, 379
               mechanical loads, 369           poloidal field coil, 379
               strength and life-time, 370     problem statement, 366
              structural and functional materials, 388, 389  toroidal and poloidal field systems, 367
              tokamak load-bearing structures, stress–  Magnet system, 23
                 strain state of               central solenoid and correction coils, 50
               accident scenarios, 365         implementation, 45
               ITER TFC, global model of, 362  international R&D programme, 45
               ITER TFC, stress state of, 362  niobium–tin intermetallic compound, 45
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