DocumentCode :
2761560
Title :
Twenty-First IEEE/NPS Symposium on Fusion Engineering 2005
fYear :
2005
fDate :
26-29 Sept. 2005
Firstpage :
1
Lastpage :
287
Abstract :
The following topics were covered: fusion development and experimental devices; large helical device; Wendelstein design; Tokamak design; IFE technology; fast ignition inertial confinement fusion reactor chamber; spherical foam targets; inertial electrostatic confinement; W7-X magnet system technology; ITER central solenoid; superconducting coils; National Compact Stellarator Experiment; ITER blanket module; ITER shielding design; vacuum vessels; vacuum pumping; plasma fueling; ITER burning plasma; plasma facing materials; plasma materials interactions; ITER neutral beam injection heating; current drive system; ITER ion cyclotron heating; ITER diagnostics; data acquisition; plasma control system; ignitor electric pulsed power system; radiological safety analysis; waste disposal
Keywords :
Tokamak devices; data acquisition; fusion reactor blankets; fusion reactor design; fusion reactor ignition; fusion reactor instrumentation; fusion reactor reaction chamber; fusion reactor safety; fusion reactor targets; plasma beam injection heating; plasma diagnostics; plasma inertial confinement; plasma radiofrequency heating; plasma-wall interactions; pulsed power supplies; radiation protection; radioactive waste disposal; stellarators; superconducting coils; vacuum pumps; IFE technology; ITER blanket module; ITER burning plasma; ITER central solenoid; ITER design; ITER diagnostics; ITER ion cyclotron heating; ITER neutral beam injection heating; ITER shielding design; National Compact Stellarator Experiment; Tokamak design; W7-X magnet system technology; Wendelstein design; current drive system; data acquisition; experimental devices; fast ignition inertial confinement fusion reactor chamber; fusion development; ignitor electric pulsed power system; inertial electrostatic confinement; large helical device; plasma control system; plasma facing materials; plasma fueling; plasma materials interactions; radiological safety analysis; spherical foam targets; superconducting coils; vacuum pumping; vacuum vessels; waste disposal;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Fusion Engineering 2005, Twenty-First IEEE/NPS Symposium on
Conference_Location :
Knoxville, TN
Print_ISBN :
0-4244-0159-6
Type :
conf
DOI :
10.1109/FUSION.2005.252996
Filename :
4019030
Link To Document :
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