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Proceedings of the 19th IEEE/IPSS Symposium on Fusion Engineering. 19th SOFE (Cat. No.02CH37231)

 

 

 

 

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Determination of the CICC joint length by transposition of the cable strands
- Trang 380-383
You-hua Zhu
In an integrated structure low resistance CICC Joint, current is conducted by outer cable strands coming into touch with the conductive Cu sole. So it is an important condition for the satisfying joint performance that each strand of the cable inside the joint is able to come to the outermost of the cable by transposition. This paper presents analysis, calculation and figures for the strand transp... hiện toàn bộ
#Spirals #Superconducting cables #Coils #Conductors #Equations #Plasmas #Contracts #Superconductivity #Steel #Wrapping
Toroidal Field Model Coil geometry survey
- Trang 213-216
C. Talarico, A. Lo Bue, L. Semeraro, F. Hurd, C. Cassani
The Toroidal Field Model Coil (TFMC) is a 36 tons "race-track" shaped coil about 4 m high and 3 m wide scaled with respect to the full-size ITER TF coils and including the key technical features and manufacturing approaches foreseen for the actual ITER TF coils. The objective of the TFMC Project is to develop and demonstrate the superconducting magnet technology to a level that will allow the ITER... hiện toàn bộ
#Solid modeling #Geometry #Assembly #Superconducting coils #Virtual manufacturing #Superconducting magnets #Steel #Computer simulation #Laser modes #Information retrieval
Progress of the KSTAR tokamak engineering
- Trang 448-453
J.S. Bak, M. Kwon, G.S. Lee
The KSTAR tokamak is under construction with aim of establishing a scientific and technological basis for an attractive fusion reactor. The KSTAR tokamak system consists of a vacuum vessel, magnet systems, in-vessel components, a cryostat, thermal shields, a vacuum pumping system, and ancillary systems. These systems are in the final stage of engineering design and prototype manufacturing with ind... hiện toàn bộ
#Tokamaks #Vacuum systems #Prototypes #Fusion reactor design #Magnetic shielding #Design engineering #Magnetic analysis #Fusion reactors #Manufacturing industries #Performance analysis
Compact flexible pellet injection system for plasma fueling experiments
- Trang 76-79
S.K. Combs, C.R. Foust, L.R. Baylor, M.J. Cole, D.T. Fehling, P.W. Fisher, M.J. Gouge, R.A. Rasmussen, D.O. Sparks, J.B. Wilgen
A compact pellet injection system has been designed and constructed at the Oak Ridge National Laboratory to provide a flexible fueling system for studies in magnetic confinement fusion devices. The system, referred to as a "pellet injector in a suitcase," is a pipe gun device with a four-barrel capability (1- to 4-mm bore), and it uses a cryogenic refrigerator for in-situ hydrogen pellet formation... hiện toàn bộ
#Plasma confinement #Instruments #Plasma devices #Laboratories #Magnetic confinement #Boring #Cryogenics #Refrigeration #Hydrogen #Acceleration
Boronization using deuterated-decaborane in JT-60U
- Trang 388-391
J. Yagyu, T. Arai, A. Kaminaga, K. Kizu, M. Arai, N. Miya
In JT-60U, boronization using hydride-decaborane (B/sub 10/H/sub 14/) vaporization has been conducted for the first wall conditioning. Compared to other discharge cleaning, boronization is claimed to be efficient in reduction of both oxygen impurities and hydrogen recycling in plasma. However, there are a few issues for reducing of hydrogen included in boron film and for stabilizing of DC glow dis... hiện toàn bộ
#Helium #Boron #Hydrogen #Plasmas #Tokamaks #Cleaning #Impurities #Recycling #Isotopes #Weight control
Effects of operating parameters on the beam species of DIII-D neutral beam ion sources
- Trang 40-43
R. Hong, H.K. Chiu
The DIII-D fusion science research facility employs positive-ion based neutral beam ion sources for plasma heating and current drive experiments. Ion species produced inside the arc chamber of an ion source determine the composition of the neutral beams injected into the plasma and in turn affect the energy deposition along the cross section of the plasma. Arc chamber design and operation schemes ... hiện toàn bộ
#Ion beams #Ion beam effects #Ion sources #Plasma sources #Particle beams #Arc discharges #Deuterium #Plasma temperature #Nuclear and plasma sciences #Heating
Computer and network infrastructure of the National Spherical Torus Experiment
- Trang 238-241
P. Roney, K. Tindall, S. Davis
The National Spherical Torus Experiment (NSTX) began acquiring data in February 1999. From the beginning it utilized a heterogeneous collection of computer platforms for control, data acquisition, analysis and. security. Computer processing, data acquisition and storage, and network capacity have been subsequently increased. The variety of platforms used for data acquisition and analysis, as well ... hiện toàn bộ
#Computer networks #Data acquisition #Data analysis #Videoconference #Communication system control #Computer security #Data security #National security #Protocols #Ethernet networks
Proceedings of the 19th IEEE/IPSS Symposium on Fusion Engineering. 19th SOFE (Cat. No.02CH37231)
- 2002
Presents the front cover of the proceedings record.
Thermal design of GA ECH launcher mirror for long pulse operation
- Trang 137-139
C.B. Baxi, M.E. Friend, J.L. Doane, E.E. Reis, R.W. Callis
Each GA ECH launcher mirrors is used to transmit 800 kW of power to the plasma. Until 2000, the pulse length for use of these mirrors was limited to 2 s due to temperatures of the mirrors resulting from 1) a high ratcheted bulk temperature and 2) a large increase in temperature of the mirror during the pulse. A new design was proposed and implemented which has extended the capability of the mirror... hiện toàn bộ
#Mirrors #Plasma temperature #Plasma measurements #Propagation losses #Plasma waves #Tokamaks #Cooling #Conductivity #Finite element methods #Length measurement
Recent results and future plan on JT-60U
- Trang 276-281
S. Ishida
Recently, JT-60U has intensively addressed enhancement and long sustainment of steady state performance in the use of negative-ion based neutral beam injection (N-NBI) and electron cyclotron (EC) wave injection. The N-NBI increased the current drive efficiency up to 1.55/spl times/10/sup 19/ A/m/sup 2//W at 360 keV and enhanced the fusion triple product up to n/sub i/(0)/spl tau//sub E/T/sub l/(0)... hiện toàn bộ
#Plasma temperature #Plasma waves #Plasma confinement #Plasma materials processing #Steady-state #Tokamaks #Inductors #Electron beams #Cyclotrons #Heating