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

 

 

 

 

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Thermal response and thermal-hydraulic analysis of PFC baking for SST-1 tokamak
- Trang 469-472
P. Chaudhuri, D.C. Reddy, S. Khirwadkar, N.R. Prakash, P. Santra, Y.C. Saxena
Steady state Superconducting Tokamak (SST-1) to address some of the physics and technology issues related to steady state tokamak operation. The plasma facing components (PFC) of SST-1, placed inside the vacuum vessel (VV) of the tokamak, are designed to be compatible for steady state operation. The main consideration in the design of the PFC is the steady state heat removal of up to 1 MW/m/sup 2/...... hiện toàn bộ
#Tokamaks #Steady-state #Plasma temperature #High temperature superconductors #Superconducting coils #Nitrogen #Thermal loading #Impurities #Heat transfer #Physics
A multi-channel phase detector using programmable logic devices
- Trang 99-102
N. Greenough, S. DePasquale, D. Lafrance
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...... hiện toàn bộ
#Phase detection #Detectors #Programmable logic devices #Logic programming #Programmable logic arrays #Field programmable gate arrays #Logic devices #Electronic equipment #Circuits #Computer errors
NCSX electrical power systems
- Trang 72-75
S. Ramakrishnan, C. Neumeyer, R. Hatcher, R. Marsala, E. Baker, H. Schneider, W. Reiersen
The National Compact Stellarator Experiment (NCSX) is being designed to be built in the existing facilities at Princeton Plasma Physics Laboratory (PPPL). The design of the NCSX electrical power system is tailored to suit the available infrastructure and electrical equipment on site. The equipment at PPPL is located primarily in two sites called C-Site and D-Site. D-Site houses the majority of ele...... hiện toàn bộ
#Power systems #Power supplies #Hardware #Plasmas #Physics #Laboratories #Circuit testing #Time factors #Coils #Thyristors
Design of the NSTX heating and cooling system
- Trang 230-233
M. Kalish, M. Cropper, C. Neumeyer, R. Parsells, L. Dudek, A. Klink, L. Morris
NSTX requires that its internal plasma facing components (PFCs) reach 350/spl deg/C during "bakeout" conditioning of the vacuum vessel. This paper describes a helium system designed to meet this requirement as well as provide cooling during plasma operations. The NSTX vacuum vessel's PFCs were designed to be heated or cooled by flowing a fluid medium through tubing attached to the PFC's copper bac...... hiện toàn bộ
#Heating #Cooling #Plasma temperature #Helium #Heat transfer #Impurities #Tiles #Physics #Copper #Atmosphere
A toroidal liquid lithium limiter for CDX-U
- Trang 341-344
R. Majeski, G. Antar, M. Boaz, D. Buchenauer, L. Cadwallader, R. Causey, R.W. Conn, R. Doerner, P. Efthimion, M. Finkenthal, D. Hoffman, B. Jones, R. Kaita, H. Kugel, S. Luckhardt, R. Maingi, M. Maiorano, T. Munsat, S. Raftopoulos, T. Rognlein, J. Spaleta, V. Soukhanovskii, D. Stutman, G. Taylor, J. Timberlake, M. Ulrickson, D. Whyte
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 ...... hiện toàn bộ
#Lithium #Physics #Plasma diagnostics #Inductors #Testing #Laboratories #Steel #Surface discharges #Heating #Rails
Tritium behavior on SiC
- Trang 164-167
K. Katayama, M. Nishikawa, T. Takeishi
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...... hiện toàn bộ
#Silicon carbide #Surface fitting #Hydrogen #Isotopes #Fusion reactors #Temperature distribution #Kinetic theory #Curve fitting #Inductors #Steel
Computer and network infrastructure of the National Spherical Torus Experiment
- Trang 238-241
P. Roney, K. Tindall, S. Davis
The National Spherical Torus Experiment (NSTX) began acquiring data in February 1999. From the beginning it utilized a heterogeneous collection of computer platforms for control, data acquisition, analysis and. security. Computer processing, data acquisition and storage, and network capacity have been subsequently increased. The variety of platforms used for data acquisition and analysis, as well ...... hiện toàn bộ
#Computer networks #Data acquisition #Data analysis #Videoconference #Communication system control #Computer security #Data security #National security #Protocols #Ethernet networks
Tính toán tải trọng gián đoạn sử dụng mô phỏng điện từ tạm thời bằng ANSYS cho các ăng-ten Alcator C-Mod Dịch bởi AI
- Trang 27-30
P.H. Titus
ANSYS đã được sử dụng để tính toán tải trọng dòng xoáy trong các thành phần ăng-ten của C-Mod do một sự gián đoạn. Các ăng-ten nằm ở mặt phẳng giữa bên ngoài, xa cách với sự tham gia trực tiếp của dòng halo, đặc trưng cho tải trọng trong bộ chuyển hướng phía trong và tường. Chỉ các dòng điện dẫn từ được tính toán. Một mô hình điện từ khá phức tạp nhưng có thể quản lý được đã được sử dụng. Ba ăng-t...... hiện toàn bộ
#Các hiện tượng điện từ #ăng-ten tải #mô phỏng plasma #phụ kiện ăng-ten #dòng xoáy #độ dẫn điện #mô hình tính toán #mô hình hóa điện từ #cuộn dây #động lực học từ tính chất lỏng
Modeling of spherical torus plasmas for liquid lithium wall experiments
- Trang 368-371
R. Kaita, S. Jardin, B. Jones, C. Kessel, R. Majeski, J. Spaleta, R. Woolley, L. Zakharov, B. Nelson, M. Ulrickson
Liquid metal walls have the potential solve to first-wall problems for fusion reactors, such as heat load and erosion of dry walls, neutron damage and activation, and tritium inventory and breeding. In the near term, such walls can serve as the basis for schemes to stabilize magnetohydrodynamic (MHD) modes. Furthermore, the low recycling characteristics of lithium walls can be used for particle co...... hiện toàn bộ
#Lithium #Magnetohydrodynamics #Plasma simulation #Surface discharges #Eddy currents #Fusion reactors #Neutrons #Recycling #Plasma properties #Fault location
Models for automated tube performance calculations
- Trang 95-98
C. Brunkhorst
High power RF systems, as typically used in fusion research devices, utilize vacuum tubes. Evaluation of vacuum tube performance involves data taken from tube operating curves. The acquisition of data from such graphical sources is a tedious process. A simple modeling method is presented that will provide values of tube currents for a given set of element voltages. These models may be used as subr...... hiện toàn bộ
#Voltage #Impedance #Electron tubes #Cathodes #Power system modeling #Radio frequency #Radiofrequency amplifiers #Polynomials #Plasma devices #Plasma sources