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

 

 

 

 

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Các bài báo tiêu biểu

High power density ion cyclotron antennas for next step device (applications)
- Trang 324-328
G. Bosia, G. Agarici, B. Beaumont, S. Bremond, K. Vulliez
Although it is generally recognized that the current IC technology is applicable to next step devices, the capability of current IC antennas to efficiently couple power to next step plasma is sometimes questioned. The ITER design effort has identified requirements for an acceptable performance. ITER-like IC antennas, fulfilling or possibly exceeding ITER requirements and designed for long pulse op... hiện toàn bộ
#Cyclotrons #Plasma devices #Radio frequency #Impedance #Loaded antennas #Plasma density #Voltage #Assembly #Plasma applications #Heating
Overview of the TFTR D&D program
- Trang 465-468
S. Raftopoulos, G. Barnes, J. Chrzanowski, J. DiMattia, R. Fedder, D. Gallagher, E. Gilsenan, G. Gettelfinger, R. Jakober, J. Laneski, P. LaMarche, R. Lindenberg, R. Parsells, E. Perry, K. Rule, J. Semler, J. Stacy, M. Viola, I. Zatz, W. Zimmer
The Tokamak Fusion Test Reactor (TFTR) operated for 15 years, from 1982 to 1997. From November 1993 to April 1997 a mixture of deuterium-tritium (D-T) was used to fuel experiments, leaving the reactor system in an activated and contaminated state. In this condition, the removal of the TFTR and its subsystems is greatly complicated. In 1999, PPPL commenced the TFTR Decontamination and Decommissioni... hiện toàn bộ
#Hazards #Vacuum systems #Inductors #Tokamaks #Surface contamination #Testing #Decontamination #US Department of Energy #Steel #Pollution measurement
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
Polymer-derived SiC/sub f//SiC/sub m/ composite fabrication and microwave joining for fusion energy applications
- Trang 426-429
R.L. Bruce, S.K. Guharay, F. Mako, W. Sherwood, E. Lara-Curzio
Reports experimental results for the very first batch of products obtained by joining silicon carbide fiber-reinforced-silicon carbide matrix composites for fusion applications. The starting point of the work has been to fabricate and join matched pairs of SiC/sub f//SiC/sub m/ composites. The composites were joined in a microwave heating environment using preceramic polymer slurry as the joining ... hiện toàn bộ
#Polymers #Silicon carbide #Thermal stresses #Thermal conductivity #Temperature #Bars #Stress measurement #Conducting materials #Electromagnetic heating #Slurries
Measurement of the energy distribution of fast excited atoms by Doppler shift spectroscopy in an inertial-electrostatic confinement fusion device
- Trang 434-437
K. Masuda, T. Mizutani, K. Yoshikawa, K. Nagasaki, K. Takiyama, H. Toku, H. Hashimoto, A. Nagafuchi
Energy distributions of energetic neutral atoms resulted from charge-exchange reactions between accelerated ions and background atoms or molecules were measured by the Doppler shift spectroscopy in an inertial-electrostatic confinement fusion (IECF) device composed of a spherical vacuum chamber as an anode and a spherical hollow cathode grid concentrically placed in the chamber. Since ions generat... hiện toàn bộ
#Atomic measurements #Energy measurement #Doppler shift #Spectroscopy #Inertial confinement #Plasma measurements #Cathodes #Hydrogen #Helium #Voltage
Reference scenario for an advanced deuterium power plant system
- Trang 252-255
J. Sheffield, D. Batchelor, S. Zinkle, M. Sawan
The proposal is to make large deuterium (D-D) magnetic fusion power plants in which some (most) of the tritium produced by fusion is removed and stored. This tritium will ultimately decay to helium-3 that will be recycled to supplement the helium-3 produced by fusion. Thus the dominant fusion becomes that of deuterium and helium-3. The level of neutron damage is reduced very substantially from tha... hiện toàn bộ
#Deuterium #Power generation #Neutrons #Proposals #Production #Plasmas #Recycling #Laboratories #Cyclotrons #Alpha particles
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
Safety and environmental considerations in the selection of fusion power plant design options
- Trang 107-110
N.P. Taylor
The neutron shielding provided by in-vessel components of a fusion power plant has an important influence on the safety and environmental performance. A number of issues related to the in-vessel shield design have been investigated, with a focus on waste minimization. Viable concepts have been identified to solve the conflict between low short-term decay heat and low long-term waste requirements, ... hiện toàn bộ
#Safety #Power generation #Neutrons #Waste management #Waste heat #Coolants #Design optimization #Waste materials #Material storage #Magnetic materials
Selection of plasma-facing materials in next-step fusion devices
- Trang 311-320
G. Federici, V. Barabash, G. Janeschitz, R. Tivey, A. Loarte, J. Roth, C.H. Skinner, W.R. Wampler
Designing a robust interface between a thermonuclear plasma and the solid material environment remains a major challenge for next-step fusion devices and future power fusion reactors. Challenging trade-offs in material choice for plasma-facing components were identified in the internationally co-ordinated R&D program supporting the Engineering Design Activities of the ITER project. This paper surv... hiện toàn bộ
#Plasma devices #Plasma materials processing #Fusion reactor design #Plasma applications #Robustness #Solids #Fusion reactors #Research and development #Design engineering #Power engineering and energy
Design of the Quasi-Poloidal Stellarator Experiment (QPS)
- Trang 248-251
B.E. Nelson, R.D. Benson, L.A. Berry, A.B. Brooks, M.J. Cole, P.J. Fogrty, P.L. Goranson, P. Heitzenroeder, S.P. Hirschman, G.H. Jones, J.F. Lyon, P.K. Mioduszewski, D.A. Monticello, D.A. Spong, D.J. Strickler, A.S. Ware, D.E. Williamson
The engineering design status of the Quasi-Poloidal Stellarator Experiment (QPS) is presented. The purpose, configuration, and possible manufacturing and assembly techniques of the various components of the core are described.
#Coils #Plasma temperature #Laboratories #Physics #Magnetic cores #Toroidal magnetic fields #Heating #Power supplies #Geometry #Copper