Page 458 - Fundamentals of Magnetic Thermonuclear Reactor Design

Index 435

Energy discharge units, 342 divertor assembly adjustment and
Enterprise Quality Management System, 62 reconfiguration, 230
Equivalent dose, 424 divertor design, 226
Error field correction divertor target, 226
field perturbation harmonic analysis, 271 start-up and final stages, 227
ITER correction coils, 273 start-up limiters, 227
plasma processes, 270 technological and testing facilities, 230
European EN 13445-6, 384 tokamak first wall configuration, 229
European blanketsHCPB, 301 vertical targets, 227
HCLL, 302 long-cycle reactors, 215
TAURO, 309 material selection, 222
EVOLVE blanket (United States), 309 next-generation reactor
Extra protective make switch (EPMS), cooling mode optimisation, 242
332, 348 DEMO reactor plasma, 236
engineering techniques, 240
eroded surface extension, 238
F erosion lifetime issue, 237
Fast discharge resistor (FDR), 332, 333 heat load increasing methods, 239
Fast discharge units (FDU), 330, 331, 344 liquid metals, 242
MCB, 331 multichannel target, 238
parameters, 332, 340 sputtered atoms deposit, 238
PB, 331 tokamak divertor operating conditions, 237
Fast disconnect switch (FDS), 346 operation mode optimisation and
Fast make switch (FMS), 344, 346 transition, 215
Fast-open switch (FOS), 338–340, 345 optical integrity and cooling system, 212
FE Meshing physical and technological ability, 215
3D FE meshes, massive conducting plasma characteristics, 212
structures, 113 short-cycle experimental devices, 215
shell models, for ITER components, 111 strength and fatigue lifetime, 225
TORNADO FE mesh, 113 structural materials and design solutions, 211
TORNADO code, 104 thickness criteria and temperature field, 222
Ferritic steels, 391 tritium accumulation, 215
Ferritic martensitic steels, 391 French Quality Order, 64
FFHR-2 blanket (Japan), 309 French RCC-MR design rules, 64
Finite-element method (FEM) Fusion power plant (FPP), 13
global, 356 Fusion reactor safety
KSTAR tokamak CS, 361 ABDB, 405
periodicity cell, 356, 357 AWDB, 405
PF1 coil segment, 358 definition, 405
First wall (FW) safety of, 422
armour erosion lifetime, 224 general purpose, 406
Coolant’s parameter determination, 221 harmful factors, 402, 403
design algorithm, 216 incident conditions, 405
ELM effects, 212 ITER radiation safety
first-wall technologies, 245 design principles for normal and off-
fuel capacitance problem, 215 normal situations, 414
heat load estimation, 221 normal operation, 415, 419
inertness, 215 radiation protection principles
initial stage design, 219 depth protection principle, defence in,
ITER 407, 408
carbon composite material (CFC), 230 expediency substantiation principle, 407
destructive events, prevention of, 234 optimisation principle, 407
discharge chamber area, 229 radiation safety criteria, 406