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
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
Engineering status and plans for the Fusion Ignition Research Experiment (FIRE)
- Trang 296-299
The FIRE project is being pursued as a possible option for the next step in the US magnetic fusion energy program. Its goal is to develop a compact, high field, highly shaped tokamak with the following parameters: major radius, R, of 2.14 m: minor radius, a, of 0.595 m.: a toroidal field on axis of 10 T; a plasma current of 7.7 MA, a flat top time of approximately 20 s, and fusion power of 150 MW.......
#Ignition #Fires #Costs #Power engineering and energy #Toroidal magnetic fields #Tokamaks #Plasmas #Nitrogen #Copper #Magnets
Nghiên cứu và thiết kế thủy nhiệt của các thành phần tiếp xúc plasma (PFC) làm mát bằng nước cho tokamak SST-1 Dịch bởi AI
- Trang 422-425
Các thành phần tiếp xúc plasma (PFC) là một phần quan trọng trong thiết kế của Tokamak Siêu dẫn Chế độ Bền (SST-1). PFC của SST-1 bao gồm các thiết bị rẽ dòng, các thiết bị ổn định thụ động, các vách ngăn và các giới hạn, được thiết kế để tương thích với hoạt động chế độ bền. Điều quan trọng nhất trong thiết kế PFC là khả năng tản nhiệt ổn định lên tới 1 MW/m/sup 2/. Trong quá trình vận hành ổn đị......
#Tokamaks #Steady-state #Tiles #Cooling #Surface fitting #Temperature distribution #Thermal loading #Coolants #Plasma temperature #Finite difference methods
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
Author index
- Trang 493-497 - 2002
The author index contains an entry for each author and coauthor included in the proceedings record.
Design and manufacture of the Toroidal Pump Limiter-start up version for the CIEL project
- Trang 348-351
After a one year shutdown devoted to the installation of Tore Supra new components (CIEL project) and the associated diagnostics, the first experimental campaign is mainly dedicated to the qualification of these high heat flux components and the general commissioning of the machine. Because of the delay of delivery of the high flux components (so-called fingers) and in order to enable the qualific......
#Manufacturing #Fingers #Toroidal magnetic fields #Magnetic field measurement #Qualifications #Protection #Plasma measurements #Insulation #Delay #Pumps
The Alcator C-Mod lower hybrid current drive experiment low power microwave and active control system
- Trang 23-26
A 3 MW (upgradeable to 4 MW) 4.6 GHz Lower Hybrid Current Drive (LHCD) system is being implemented on Alcator C-Mod to control and sustain current profile evolution. The LHCD low-power microwave and active control system, using fast vector modulators, will provide a phase and amplitude controlled driver for each of twelve 4.6 GHz, 250 kW klystrons. Resulting phase and power outputs of each klystro......
#Control systems #Klystrons #Phase modulation #Amplitude modulation #Monitoring #Gunshot detection systems #Phase detection #Detectors #Plasmas #Digital control