Title :
Proceedings of the 22nd IEEE/NPSS Symposium on Fusion Engineering - SOFE 07
Abstract :
The following topics are dealt with: divertor engineering; plasma materials interactions; inertial fusion targets; shield design; NCSX construction; advanced fusion devices; tritium systems; fusion materials; inertial fusion engineering; superconducting bus-bar system; Wendelstein 7-X; ITER magnet design criteria; lithium Tokamak experiment; liquid lithium; phase lag infrared thermal examination; compact stellarator reactor; ITER neutronics analysis; ATTILA discrete ordinates software; MCAM; integrated automatic modeling system; solid electrolyte; nuclear fusion blanket; water hydraulic remote handling system; metrology; pellet dropper device; high pressure supersonic gas jet fueling; DIII-D field shaping coils; dynamic temperature-profile modelling; laser fusion; helium-cooled porous tungsten heat exchanger concept; material surface ablation; ultrasonic non-destructive evaluation; national ignition facility; Sandia´s Z-pinch accelerator; fast ignition realization experiment; EU-HCPB-TBM design; two-phase flows; heat transfer; dual-coolant waste transmutation blanket; high temperature DEMO blanket; dynamic tritium recycling; MHD analysis; Korean helium cooled molten lithium TBM; single stage pneumatic pellet injector; SST-1 Tokamak; inertial fusion energy power reactor; W7-X magnet support structure; national high-power advanced torus experiment; direct drive laser fusion chamber; ARIES-CS power plant; dose measurement; CFD analysis; preliminary probabilistic safety assessment; hydrogen separating membrane research; hydrogen isotope retention; target materials physics; DENIM; output LC filter; JET enhanced radial field amplifier; ICRH systems; lower hybrid current drive system design; energy storage; tunable reflectometry system; limiter thermography; vacuum vessel external flux loops; imaging bolometer upgrade; FPGA-based pulse-oriented digital acquisition system; nuclear detectors; control system; remote handling; thermo-fluid exploratory design analysis; damage-- resistant metal mirrors; and ITER diagnostic port plug engineering design.
Keywords :
Tokamak devices; accelerator-based transmutation; bolometers; computational fluid dynamics; control systems; data acquisition; dosimetry; energy storage; fusion reactor blankets; fusion reactor design; fusion reactor divertors; fusion reactor safety; fusion reactor targets; heat exchangers; heat transfer; high energy physics instrumentation computing; infrared imaging; laser ablation; laser fusion; liquid metals; lithium; neutron activation analysis; nuclear reactor maintenance; plasma diagnostics; plasma magnetohydrodynamics; plasma materials processing; plasma-wall interactions; radioactive waste; reflectometry; remote handling; shielding; solid electrolytes; stellarators; tritium handling; tungsten; two-phase flow; ultrasonic materials testing; ARIES-CS power plant; ATTILA discrete ordinates software; CFD analysis; DENIM; DIII-D field shaping coils; EU-HCPB-TBM design; FPGA-based pulse-oriented digital acquisition system; ICRH systems; ITER diagnostic port plug engineering design; ITER magnet design criteria; ITER neutronics analysis; JET enhanced radial field amplifier; Korean helium cooled molten lithium TBM; Li; MCAM; MHD analysis; NCSX construction; SST-1 Tokamak; W; W7-X magnet support structure; Wendelstein 7-X; Z-pinch accelerator; advanced fusion devices; compact stellarator reactor; control system; damage-resistant metal mirrors; direct drive laser fusion chamber; divertor engineering; divertor maintenance; dose measurement; dual-coolant waste transmutation blanket; dynamic temperature-profile modelling; dynamic tritium recycling; energy storage; fast ignition realization experiment; fusion materials; heat transfer; helium-cooled porous tungsten heat exchanger concept; high pressure supersonic gas jet fueling; high temperature DEMO blanket; hydrogen isotope retention; hydrogen separating membrane research; imaging bolometer upgrade; inertial fusion energy power reactor; inertial fusion engineering; inertial fusion targets; integrated automatic modeling system; laser fusion; limiter thermography; liquid lithium; lithium Tokamak experiment; lower hybrid current drive system design; material surface ablation; metrology; national high-power advanced torus experiment; national ignition facility; nuclear detectors; nuclear fusion blanket; output LC filter; pellet dropper device; phase lag infrared thermal examination; plasma materials interactions; probabilistic safety assessment; remote handling; shield design; single stage pneumatic pellet injector; solid electrolyte; superconducting bus-bar system; target materials physics; thermo-fluid exploratory design analysis; tritium systems; tunable reflectometry system; two-phase flows; ultrasonic nondestructive evaluation; vacuum vessel external flux loops; water hydraulic remote handling system;
Conference_Titel :
Fusion Engineering, 2007. SOFE 2007. 2007 IEEE 22nd Symposium on
Conference_Location :
Albuquerque, NM
Print_ISBN :
978-1-4244-1193-1
Electronic_ISBN :
978-1-4244-1194-8
DOI :
10.1109/FUSION.2007.4337856
