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

Công bố khoa học tiêu biểu

* Dữ liệu chỉ mang tính chất tham khảo

Sắp xếp:  
Selection of plasma-facing materials in next-step fusion devices
Proceedings of the 19th IEEE/IPSS Symposium on Fusion Engineering. 19th SOFE (Cat. No.02CH37231) - - 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
Post-test calculations with ISAS-ITER system for ICE experiments
Proceedings of the 19th IEEE/IPSS Symposium on Fusion Engineering. 19th SOFE (Cat. No.02CH37231) - - Trang 48-51
M.T. Porfiri, P. Meloni
In the frame of the Safety and Environment tasks of the European Technology Program for ITER project one of the main issue is the validation of the computer codes and models used as reference for ITER safety analysis to obtain acceptance by licensing authorities. In the context of the fusion field facilities the data useful for validation are very limited because only few experimental machines are...... hiện toàn bộ
#Ice #Safety #Testing #Licenses #Coolants #Computational modeling #Computer simulation #Containers #Plasma simulation #Analytical models
Thermal response and thermal-hydraulic analysis of PFC baking for SST-1 tokamak
Proceedings of the 19th IEEE/IPSS Symposium on Fusion Engineering. 19th SOFE (Cat. No.02CH37231) - - 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
Design of the P2001 ECH launcher for DIII-D
Proceedings of the 19th IEEE/IPSS Symposium on Fusion Engineering. 19th SOFE (Cat. No.02CH37231) - - Trang 133-136
R. Ellis, J. Hosea, J. Wilson, L. Gereg, R. Prater, R. Callis, H. Grunloh
ECH launchers typically use a moveable mirror to steer a gyrotron beam. Increased power handling capability in an ECH launcher requires adding mass or active cooling to the mirrors. The additional forces on the moveable mirror resulting from either approach typically require a compromise between the power handling capability and the steering capability. The P2001 launcher, designed by PPPL for DII...... hiện toàn bộ
#Mirrors #Thermal conductivity #Steel #Cooling #Copper #Electromagnetic forces #Conducting materials #Position measurement #Plasma temperature #Magnetic materials
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
Proceedings of the 19th IEEE/IPSS Symposium on Fusion Engineering. 19th SOFE (Cat. No.02CH37231) - - 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
Results from the MAST spherical tokamak
Proceedings of the 19th IEEE/IPSS Symposium on Fusion Engineering. 19th SOFE (Cat. No.02CH37231) - - Trang 454-460
A. Sykes, J.-W. Ahn, R.J. Akers, E. Arends, K. Axon, R.J. Buttery, C. Byrom, P.G. Carolan, D. Ciric, N.J. Conway, M. Cox, G.F. Counsell, G. Cunningham, A.C. Darke, J. Dowling, M.R. Dunstan, A.R. Field, S.J. Fielding, S. Gee, M. Gryaznevich, R.J. Hayward, P. Helander, M.B. Hood, A. Kirk, I. Lehane, B. Lloyd, G.P. Maddison, S.J. Manhood, R. Martin, G.J. McArdle, H. Meyer, M. Mgrath, A.W. Morris, M.P.S. Nightingale, T. Pinfold, M.N. Price, C. Ribeiro, D.C. Robinson, V. Shevchenko, K. Stammers, A. Tabasso, D. Taylor, M. Tournianski, M. Valovic, G.M. Voss, M.J. Walsh, S.E.V. Warder, H.R. Wilson
The MAST (Mega-Amp Spherical Tokamak) experiment has been operational since Jan 2000. Results from MAST are important both in evaluating the potential of future ST fusion devices, and in developing understanding of processes relevant to conventional aspect ratio tokamaks. In this paper methods of initiating, ramping up, and sustaining the high plasma currents associated with ST fusion devices are ...... hiện toàn bộ
#Tokamaks #Heating #Physics #Solenoids #Educational institutions #Plasma devices #Plasma diagnostics #Particle beams #Plasma applications #Plasma density
NCSX electrical power systems
Proceedings of the 19th IEEE/IPSS Symposium on Fusion Engineering. 19th SOFE (Cat. No.02CH37231) - - 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
Engineering design study of JT-60 superconducting modification
Proceedings of the 19th IEEE/IPSS Symposium on Fusion Engineering. 19th SOFE (Cat. No.02CH37231) - - Trang 221-225
A. Sakasai, S. Ishida, M. Matsukawa, G. Kurita, N. Akino, T. Ando, T. Arai, H. Ichige, A. Kaminaga, T. Kato, K. Kizu, K. Masaki, Y.M. Miura, Y. Miyo, A. Morioka, S. Sakurai, T. Sasajima, S. Takeji, H. Tamai, K. Tsuchiya, K. Urata, J. Yagyu, K. Tobita, H. Takenaga, K. Shimizu, M. Kikuchi
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...... hiện toàn bộ
#Design engineering #Superconducting coils #Inductors #Plasma materials processing #Steel #Superconducting magnets #Tokamaks #Power generation economics #Environmental economics #Steady-state
Status and plan of the HL-2A project
Proceedings of the 19th IEEE/IPSS Symposium on Fusion Engineering. 19th SOFE (Cat. No.02CH37231) - - Trang 461-464
Jiancheng Yan, Caipin Zhou, Yong Liu, Dequan Liu
This paper describes the outline of HL-2A project that is the first tokamak with a divertor in China. The recent achievements in the construction of the HL-2A tokamak is given. The development of major components and the installation of the machine are also described. The commissioning of HL-2A machine will start from the middle of 2002. The HL-2A experimental program and the future plan are sketc...... hiện toàn bộ
#Tokamaks #Coils #Pulsed power supplies #Plasma confinement #Variable speed drives #Vacuum systems #Power generation #Shape control #Plasma diagnostics #Heating
Nuclear considerations for FIRE
Proceedings of the 19th IEEE/IPSS Symposium on Fusion Engineering. 19th SOFE (Cat. No.02CH37231) - - Trang 196-199
M.E. Sawan, H.Y. Khater
Nuclear analyses have been performed for the baseline design of the Fusion Ignition Research Experiment (FIRE). Nuclear heating, structural radiation damage, and magnet insulator dose were evaluated. Critical issues requiring additional R&D effort include low-temperature embrittlement of copper and identifying insulators that can handle a dose as high as 1.5/spl times/10/sup 10/ Rads under the FIR...... hiện toàn bộ
#Fires #Copper #Heating #Tiles #Insulation #Performance analysis #Coils #Space vector pulse width modulation #Leg #Thermal stresses
Tổng số: 115   
  • 1
  • 2
  • 3
  • 4
  • 5
  • 6
  • 10