Proceedings of the 19th IEEE/IPSS Symposium on Fusion Engineering. 19th SOFE (Cat. No.02CH37231)
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Modeling of mirror surface damage effects on beam performance in a laser-driven IFE power plant
- Trang 118-121
Grazing incidence metal mirrors in laser-driven IFE power plants are subject to a variety of threats that result in damages leading to increased laser absorption, beam quality degradation and reduced laser-induced damage threshold. In this paper, we analyze the mirror reflectivity changes and wavefront distortions incident on the target using several modeling approaches, depending on the nature an......
#Mirrors #Surface emitting lasers #Laser beams #Laser modes #Power lasers #Power generation #Laser noise #Reflectivity #Degradation #Surface contamination
Impact of low PRF tritium permeation barriers-on the water cooled lead lithium blanket: A safety analysis
- Trang 356-359
A summary is here presented concerning the first results in evaluating the safety features of the European water-cooled lead lithium blanket in which tritium permeation barriers on the external surface of the breeder cooling pipes are not used or, if used, a lower efficiency is required for them. As a consequence, in this design concept, a significant amount of tritium must be recovered through th......
#Lithium #Safety #Cooling #Coolants #Circuits #Water conservation #Coatings #Physics #Fuels #Environmental economics
Thermal analysis and extended operation simulation of the DIII-D TF-coil belt bus system
- Trang 337-340
The DIII-D toroidal field [TF] belt bus system provides an electrical connection between adjacent TF-coil bundles to form a continuous current path for the TF-coil system. There is also a return path which is electrically isolated from the belt bus. The function of the system is to carry TF-coil current while minimizing the TF-coil error field in accordance with physics requirements. The system is......
#Analytical models #Belts #Physics #Contact resistance #Optical fibers #Temperature measurement #Temperature sensors #Predictive models #Insulation #Solid modeling
The Alcator C-Mod lower hybrid current drive experiment transmitter and power system
- Trang 16-19
Alcator C-Mod is a high-field, high-density, diverted, compact tokamak, which, in its present form uses inductive current drive and is heated with 5 MW of ICRF auxiliary power. C-Mod is in the process of being upgraded with a 4.6 GHz Lower Hybrid heating and current drive system. The purpose of the experiment is to develop and explore the potential of "Advanced Tokamak Regimes", i.e., regimes with......
#Hybrid power systems #Klystrons #Pulsed power supplies #Tokamaks #Power supplies #Auxiliary transmitters #Heating #Radio frequency #Control systems #Power system protection
Progress of HT-7U superconducting tokamak
- Trang 282-284
The HT-7U is a superconducting tokamak, which is constructing in Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP). The mission of the HT-7U project is to develop scientific and engineering issues on the steady state operation of advanced tokamak. The engineering design of the device is optimized. The R&D program is going on. Short samples of conductor and a central solenoid (CS) mo......
#Tokamaks #Coils #Plasma devices #Physics #Conductors #Testing #Nuclear and plasma sciences #Steady-state #Design engineering #Design optimization
A multi-channel phase detector using programmable logic devices
- Trang 99-102
Recent developments in programmable logic devices have led to in-system programming capabilities for FPGA (field programmable logic array) and CPLD (complex programmable logic device) devices using inexpensive programming heads and PC-type computers. This development has major advantages for electronic equipment used in a research setting. Many of the devices are electrically erasable and re-progr......
#Phase detection #Detectors #Programmable logic devices #Logic programming #Programmable logic arrays #Field programmable gate arrays #Logic devices #Electronic equipment #Circuits #Computer errors
Proceedings of the 19th IEEE/IPSS Symposium on Fusion Engineering. 19th SOFE (Cat. No.02CH37231)
- 2002
Presents the front cover of the proceedings record.
A toroidal liquid lithium limiter for CDX-U
- Trang 341-344
Attention has focused recently on flowing liquid lithium as a first wall for a reactor because of its potentially attractive physics and engineering features. In order to test the suitability of liquid lithium as a plasma facing component, the Current Drive eXperiment - Upgrade (CDX-U) at the Princeton Plasma Physics Laboratory has recently installed a fully toroidal liquid lithium limiter. CDX-U ......
#Lithium #Physics #Plasma diagnostics #Inductors #Testing #Laboratories #Steel #Surface discharges #Heating #Rails
High heat flux interactions and tritium removal from plasma facing components by a scanning laser
- Trang 473-476
A new technique for studying high heat flux interactions with plasma facing components is presented. The beam from a continuous wave 300 W neodymium laser was focussed to 80 W/mm/sup 2/ and scanned at high speed over the surface of carbon tiles. These tiles were previously used in the TFTR inner limiter and have a surface layer of amorphous hydrogenated carbon that was codeposited during plasma op......
#Plasma temperature #Tiles #Plasma waves #Manufacturing #Laser beams #Neodymium #Surface waves #Surface emitting lasers #Amorphous materials #Plasma materials processing
Modeling of spherical torus plasmas for liquid lithium wall experiments
- Trang 368-371
Liquid metal walls have the potential solve to first-wall problems for fusion reactors, such as heat load and erosion of dry walls, neutron damage and activation, and tritium inventory and breeding. In the near term, such walls can serve as the basis for schemes to stabilize magnetohydrodynamic (MHD) modes. Furthermore, the low recycling characteristics of lithium walls can be used for particle co......
#Lithium #Magnetohydrodynamics #Plasma simulation #Surface discharges #Eddy currents #Fusion reactors #Neutrons #Recycling #Plasma properties #Fault location