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
Report of the FESAC panel on burning plasmas
- Trang 152-155
On October 5, 2000 Dr. Mildred Dresselhaus, then Director of the Office of
Science within the U.S. Department of Energy, instructed the Fusion Energy
Sciences Advisory Committee (FESAC) to prepare a report describing the status
and future of burning plasma physics issues within the U.S. fusion program.
FESAC formed a panel to carry out this analysis and the present paper presents a
summary of the ...
#Physics #Plasma confinement #Nuclear and plasma sciences #Alpha particles #Toroidal magnetic fields #Magnetic confinement #Plasma sources #Heating #Fusion reactors #Deuterium
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
Upgrade to the Tritium Remote Control and Monitoring System for TFTR D&D
- Trang 260-263
Since 1988, the Tritium Remote Control and Monitoring System (TRECAMS) has
performed crucial functions in support of D-T operations of the Tokamak Fusion
Test Reactor (TFTR) at the Princeton Plasma Physics Laboratory (PPPL). Although
plasma operations on TFTR were completed in 1997, the need for TRECAMS
continued. During this period TRECAMS supported the TFTR tritium systems, the
TFTR's shutdown a...
#Control systems #Remote monitoring #Plasmas #Performance evaluation #Tokamaks #System testing #Inductors #Physics #Laboratories #Decontamination
KSTAR vacuum vessel thermal shield analysis
- Trang 392-395
The KSTAR Vacuum vessel thermal shield is composed of multilayer insulation
(MLI), cryopanel and supports. One of the major design parameters for the design
of thermal shield cryopanel and supports is the eddy current induced during
plasma disruption. The eddy current creates joule heating as well as
electromagnetic (EM) loads combining with magnetic fields. Since the cryopanel
should be maintaine...
#Thermal loading #Plasma temperature #Thermal stresses #Eddy currents #Magnetic multilayers #Insulation #Electromagnetic heating #Electromagnetic fields #Electromagnetic forces #Electromagnetic shielding
Engineering design study of JT-60 superconducting modification
- Trang 221-225
The modification of JT-60 is planned as a fully superconducting tokamak
(JT-60SC). The mission of JT-60SC program is to establish scientific and
technological bases for an advanced operation in an economically and
environmentally attractive DEMO reactor and ITER. The research objectives are to
accomplish high performance steady state operation with high beta and
non-inductive full current drive, w...
#Design engineering #Superconducting coils #Inductors #Plasma materials processing #Steel #Superconducting magnets #Tokamaks #Power generation economics #Environmental economics #Steady-state
Laser-induced damage of metal mirrors under long-term exposure at shallow angle of incidence
- Trang 272-275
Laser induced damage (LID) experiments were performed with a 2-J
frequency-multiplied Nd:YAG laser at 1/2 /spl mu/m wavelength and a variety of
metal mirrors (pure and impure diamond-turned) at shallow angle of incidence to
study the sensitivity of these mirrors to LID under long term exposure.
Practical lifetime curves for Al-1100 and 99.999% pure Al mirrors have been
established up to 10/sup 4/ ...
#Mirrors #Thermal stresses #Laser beams #Surface emitting lasers #Reflectivity #Plastics #Temperature #Artificial intelligence #Optical surface waves #Surface cracks
Author index
- Trang 493-497 - 2002
The author index contains an entry for each author and coauthor included in 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