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
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......
#Spirals #Superconducting cables #Coils #Conductors #Equations #Plasmas #Contracts #Superconductivity #Steel #Wrapping
Comparison of radwaste volume and hazard in liquid wall and conventional solid wall concepts
- Trang 168-171
In this paper, we quantitatively assess the advantages offered by thick liquid wall (LW) concepts over conventional solid wall (SW) concepts in terms of the substantial reduction in radiation damage as well as activation to solid structure with subsequent reduction in radwaste volume and hazard. The conventional SW FW/blanket considered is made of Li/V with a peak neutron wall load of 5 MW/m/sup 2......
#Hazards #Solids #Neutrons #Lithium #Protection #Fusion reactors #Magnetic shielding #Frequency estimation #Life estimation #Lifetime estimation
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
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
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
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
Nonlinear burn control in fusion reactors
- Trang 430-433
Control of plasma density and temperature magnitudes, as well as their profiles, are among the most fundamental problems in fusion reactors. Unfortunately, the economy of fusion reactors often requires the reactor to operate under conditions in which the rate of thermonuclear reaction increases as the plasma temperature rises. In this thermally unstable zone, an active control system is necessary ......
#Fusion reactors #Plasma temperature #Power system modeling #Temperature control #Plasma density #Inductors #Control systems #Nonlinear equations #Control system synthesis #Adaptive control
Towards ITER construction
- Trang 1-9
Following the end of the Engineering Design Activities (EDA) in July 2001, all the essential elements are now available to make a decision to construct ITER. The design has been elaborated to the extent necessary to allow a realistic assessment of its feasibility, performance and cost at a generic site, and R&D has been carried out to underpin the design choices. The project is now entering a phas......
#Electronic design automation and methodology #Plasma confinement #Design engineering #Research and development #Magnetic confinement #Costs #Law #Legal factors #Power engineering and energy #Ignition
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
Design and engineering of the Alcator C-Mod lower hybrid current drive system
- Trang 20-22
The PSFC group of MIT and PPPL are jointly developing a Lower Hybrid Current Drive (LHCD) system for installation on the Alcator C-Mod tokamak, with the primary goal of driving plasma current. Twelve Klystrons will feed a coupler with an input power of 3 MW at 4.6 GHz and a pulse length of 5 seconds. The coupler is composed of 4 arrays, each with 24 wave-guides (96 total) which are stacked poloida......
#Design engineering #Plasma waves #Plasma sources #Klystrons #Feeds #Plasma temperature #Frequency #Physics #Plasma diagnostics #Plasma stability