The proceedings contain 155 papers on the 20th ieee/npss symposium on fusion engineering, SOFE 03. The topics discussed include: modification of the target areas of the W7-X divertor for steady-state operation;experim...
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The proceedings contain 155 papers on the 20th ieee/npss symposium on fusion engineering, SOFE 03. The topics discussed include: modification of the target areas of the W7-X divertor for steady-state operation;experimental measurement of hydrogen and helium retention on liquid lithium on FLIRE;laser ablation and heating tests performed on Tore Supra and TEXTOR graphite samples;neutronics parameters optimization of the improved dual-cooled waste transmuted blanket for the FDS;engineering description of a solid first wall blanket based on advanced ferritic steel and re-circulating flibe;and thermal-hydraulic design and optimization of the improved dual cooled waste transmutation blanket for the FDS.
The proceedings contains 131 papers. Topics discussed include inertial fusionengineering, magnet systems, plasma physics and advance devices, data acquisition and diagnostics, nuclear and material engineering, plasma...
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The proceedings contains 131 papers. Topics discussed include inertial fusionengineering, magnet systems, plasma physics and advance devices, data acquisition and diagnostics, nuclear and material engineering, plasma-material interactions, assembly, fabrication and maintenance, blanket, shield and vacuum engineering, power plant studies, natural beam injection and fueling systems and vacuum and power supply systems.
The proceedings contains 124 papers. Topics discussed include tokamak engineering and operations, safety and environment, tritium systems and tritium control, divertor and plasma-facing component engineering, heating ...
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The proceedings contains 124 papers. Topics discussed include tokamak engineering and operations, safety and environment, tritium systems and tritium control, divertor and plasma-facing component engineering, heating and current drive systems, plasma control and power systems.
The proceedings contains 186 papers. Topics discussed include neutral beam injection, divertors, control systems and data acquisition, cryopump design for radiative divertors, plasma facing components, fusion reactors...
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The proceedings contains 186 papers. Topics discussed include neutral beam injection, divertors, control systems and data acquisition, cryopump design for radiative divertors, plasma facing components, fusion reactors, plasmas, neutron activation analysis, fusion materials, stellarators, numerical simulations, safety analysis, tokamak devices, fusion power plants, inertial electrostatic confinement, tokamak physics experiment design, superconducting magnets, vacuum vessels, helium cooling systems, remote maintenance, plasma physics, solenoid design and performance, fusion economics, plasma heating and fueling.
The proceedings contain 291 papers. The topics discussed include: fusion reactor high vacuum pumping: charcoal cryosorber tritium exposure results;the design and fabrication of a toroidally continuous cryocondensation...
ISBN:
(纸本)0780301323
The proceedings contain 291 papers. The topics discussed include: fusion reactor high vacuum pumping: charcoal cryosorber tritium exposure results;the design and fabrication of a toroidally continuous cryocondensation pump for the DIII-D advanced divertor;verification test for helium panel of cryopump for DIII-D advanced divertor;design of the advanced divertor pump cryogenic system for DIII-D;optimization of thermal design for nitrogen shield of JET cryopump;diagnostics of the high-speed single-pellet injector for the Frascati tokamak upgrade;implementation of a far-infrared interferometer on the Madison symmetric torus;the charge exchange recombination diagnostic system on the DIII-D tokamak;the multipulse Thomson scattering diagnostic on the DIII-D tokamak;and investigation of induction cells and modulator design for heavy ion accelerators.
The TPX Toroidal Field (TF) and Poloidal Field (PF) Coils use both Nb3Sn and Nb-Ti internally cooled, cabled superconductor (ICCS). A prime consideration in the design of the coils was the minimization of joints in th...
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ISBN:
(纸本)0780314131
The TPX Toroidal Field (TF) and Poloidal Field (PF) Coils use both Nb3Sn and Nb-Ti internally cooled, cabled superconductor (ICCS). A prime consideration in the design of the coils was the minimization of joints in the conductor cable to save space, reduce heating losses and increase reliability. Therefore, the traditional double pancake approach was discarded in favor of the continuously wound coil. The recently developed use of the roll bender in winding the coils permits the backwinding, which is required in this geometry. The Nb3Sn TF coils, the central solenoid coils and inner-most PF coils require the wind-react-insulate sequence. The Nb-Ti outer PF Coils are also insulated after the coils are wound because the insulation system used in all the coils requires the insulation of rigid polyimide sheet between turns and pancakes before Vacuum Pressure Impregnation (VPI) of the glass epoxy system.
The proceedings contain 170 papers. The topics discussed include: IRES: a code evaluating the beamlet beamlet interaction for multi-aperture electrostatic accelerators;compensation of beamlet deflection by mechanical ...
ISBN:
(纸本)9781424426362
The proceedings contain 170 papers. The topics discussed include: IRES: a code evaluating the beamlet beamlet interaction for multi-aperture electrostatic accelerators;compensation of beamlet deflection by mechanical offset of the grids apertures in the SPIDER ion source;an overview of the iter in-vessel coil systems;progress on the ITER electron cyclotron heating and current drive upper launcher steering mirror control system;structural load specification for ITER tokamak components;jet operations and plasma control: a plasma control system that is safe and flexible in a manageable way;physics operations with the DIII-D plasma control system;design of plasma shape control system for KSTAR tokamak;experimental analysis of MHD pressure drop in a HCLL blanket mock-up;and thermo-mechanical analysis of a prototypical SiC foam-based flow channel insert.
The proceedings contain 148 papers. The topics discussed include: Korean ITER participation and activities in ITER transitional arrangements;JET enhancement programmes: key steps in the preparation of ITER;NCSX constr...
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ISBN:
(纸本)142440150X
The proceedings contain 148 papers. The topics discussed include: Korean ITER participation and activities in ITER transitional arrangements;JET enhancement programmes: key steps in the preparation of ITER;NCSX construction progress and research plans;the potential profile and its influence on the neutron yield of inertial electrostatic confinement fusion device;high temperature superconductor current leads proposal for ITER;the ITER central solenoid;thermo-mechanical analysis of ITER test unit cell under pulse operation;blanket concepts for alternate fusion energy options;evaluation of material design limits for TBM applications;neutronics assessment of blanket options for the HAPL laser inertial fusion energy chamber;neutronics features of a dual coolant lithium lead test blanket module for ITER;numerical study on splash conditions of an integrated droplet-type divertor;development of new ferritic/martensitic steels for fusion applications;NCSX vacuum vessel fabrication;and C-MOD cryopump design and analysis.
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