Proceedings of the 19th IEEE/IPSS Symposium on Fusion Engineering. 19th SOFE (Cat. No.02CH37231)
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High heat flux tests of carbon composites for KSTAR and NSTX
- Trang 345-347
Uncooled samples of various carbon fiber composites (CFCs), nominally 2.50 cm
square and 1.00 cm in height were exposed in the Electron Beam Test System
(EBTS) to heat fluxes up to /spl sim/100 MW/m/sup 2/ for shots typically of 1.5
s. The heat flux was focused on a square 1 /spl times/ 1 cm at the center of the
sample. For NSTX (National Spherical Torus Experiment), five samples of Allied
Signal ...
#Surface morphology #Aerospace testing #Tokamaks #Temperature #Thermal stresses #Aerospace industry #Electron beams #Surface cracks #Materials testing #Thermal expansion
Design of the National Compact Stellarator Experiment (NCSX) core
- Trang 285-289
The design status of the stellarator core for the National Compact Stellarator
Experiment (NCSX) is presented. The purpose, configuration, and possible
manufacturing and assembly techniques of the various components of the core are
described.
#Coils #Laboratories #Physics #Manufacturing #Plasma confinement #Plasma devices #Shape #Geometry #Copper #Conductors
Alternative structural concepts for the Fusion Ignition Research Experiment (FIRE)
- Trang 200-204
The baseline toroidal field coil system of the FIRE tokamak utilizes inertially
cooled, copper alloy Bitter plate type magnets which are LN/sub 2/ cooled
between shots. The TF configuration is wedged and uses C17510 high strength,
high conductivity beryllium copper alloy which was developed for BPX in the
inner leg, where the stress is highest. In FY 01, a slightly larger design was
adopted (R=2.1...
#Ignition #Fires #Stress #Coils #Copper alloys #Conductivity #Leg #Tokamaks #Magnets #Physics
Compact probe design for power monitoring from the narrow side of the reduced height waveguide
- Trang 268-271
Due to confined space in a stack of reduced height waveguides, power detection
of the incident and reflected wave in the reduced height waveguide is extremely
difficult. A new compact probe to monitor the incident and reflected wave from
the narrow side of the reduced height waveguide has been developed. This compact
probe consists of 2 current loops, a directional coupler, and a small trimmer
cap...
#Probes #Monitoring #Directional couplers #Impedance #Power transmission lines #Plasma confinement #Capacitors #Testing #Tokamaks #Power cables
Assembly, integration and dimensional control of the steady state tokamak SST-1
- Trang 256-259
SST-1 is a large aspect ratio tokamak designed for steady state operation,
configured to run a double/single null, elongated triangular plasma, which is
under construction in India. It has a major radius of 1.1 m with plasma minor
radius of 0.2 m, with maximum toroidal magnetic field 3 Tesla at the plasma
center. SST-1 tokamak has a large number of components to be assembled at site
to build vario...
#Steady-state #Tokamaks #Superconducting coils #Superconducting magnets #Toroidal magnetic fields #Assembly systems #Vacuum systems #Plasma devices #Feeds #Boring
Tritium behavior on SiC
- Trang 164-167
SiC (silicon carbide) has been considered as one of the primary candidate
materials for a first wall component in a future fusion reactor because it has
been claimed that SiC has excellent high temperature properties and low
activation. However, the behavior of tritium on SiC has not been discussed yet.
In this study, the tritium trapping capacity on the surface of SiC is
experimentally obtained a...
#Silicon carbide #Surface fitting #Hydrogen #Isotopes #Fusion reactors #Temperature distribution #Kinetic theory #Curve fitting #Inductors #Steel
Structural analyses and preliminary design of HT-7U cryostat
- Trang 372-375
The cryostat of HT-7U Tokamak is a large vacuum vessel surrounding the entire
Basic Machine with cylindrical shell, dished top and flat bottom. The main
function of HT-7U cryostat provides the thermal barrier between the ambient
temperature testing hall and the liquid helium cooled superconducting magnet.
The loads applied to the cryostat are vacuum pressure, dead weight, seismic
events and electr...
#Stress #Tokamaks #Plasma temperature #Testing #Helium #Superconducting magnets #Electromagnetic forces #Eddy currents #Feeds #Joining processes
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
Structural design and analysis for the KSTAR cryostat
- Trang 396-399
The KSTAR cryostat is a 8.8 m diameter vacuum vessel that provides the necessary
thermal barrier between the ambient temperature test cell and the supercritical
helium cooled superconducting magnet providing the base pressure of 1/spl
times/10/sup -5/ torr. The cryostat is a single walled vessel consisting of
central cylindrical section and two end closures, a flat base structure with
external rei...
#Magnetic analysis #Superconducting magnets #Plasma temperature #Testing #Helium #Leg #Concrete #Bellows #Thermal loading #Performance analysis
Alcator C-Mod inner divertor upgrade design and analysis
- Trang 333-336
In 1993 there were indications that the C-Mod inner divertor was being
over-loaded. As a result, an inner divertor modification is being installed in
C-Mod. The new design is intended to allow a change in profile of the divertor
to accommodate a higher plasma triangularity, strengthen the inner vessel wall
to survive 9.0 Tesla, 2.5 MA disruptions and, eliminate tile rotation. The
thermal different...
#Tiles #Thermal stresses #Plasma temperature #Thermal expansion #Contracts #Nuclear and plasma sciences #Hardware #Assembly #Tokamaks #Temperature distribution