IEEE 1989 International Conference on Plasma Science最新文献

Operation of the IGNITEX tokamak IGNITEX托卡马克的操作

IEEE 1989 International Conference on Plasma Science Pub Date : 1989-12-01 DOI: 10.1109/PLASMA.1989.166277

S. Eways, R. Carrera, J. Dong, G. Hallock, E. Montalvo

{"title":"Operation of the IGNITEX tokamak","authors":"S. Eways, R. Carrera, J. Dong, G. Hallock, E. Montalvo","doi":"10.1109/PLASMA.1989.166277","DOIUrl":"https://doi.org/10.1109/PLASMA.1989.166277","url":null,"abstract":"The operation of the IGNITEX ignition tokamak from breakdown to shutdown is discussed. The pulse length of the discharge is extended by precooling the magnet structure to liquid nitrogen temperature between pulses. RF cavity resonance is used to break down the neutral gas and initiate the plasma discharge in a controllable and reproducible way. The structure of the vacuum toroidal cavity modes has been investigated analytically. A numerical study of the field mode structure and the mode evolution during the plasma buildup has been carried out. Plasma current, equilibrium, shaping, and control are provided by an internal inductor with five pairs of single-turn coils which are independently powered by homopolar generators. Plasma coupling is maximized by the proximity of the poloidal field system to the plasma column. The conducting massive structure surrounding the plasma should damp plasma displacements. The MHD plasma equilibrium throughout a typical IGNITEX discharge has been analyzed. The IGNITEX experiment will operate basically in the L-mode without limiter. However, separatrix configurations of equilibrium are easily obtained by minor changes in the pulse shape of the elongation coils.<<ETX>>","PeriodicalId":165717,"journal":{"name":"IEEE 1989 International Conference on Plasma Science","volume":"1 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1989-12-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"129442840","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Gas-puff Z-pinch on pulsed power generator with self-crowbar switch 带自撬棍开关的脉冲发电机充气z夹紧

IEEE 1989 International Conference on Plasma Science Pub Date : 1989-12-01 DOI: 10.1109/PLASMA.1989.166142

H. Akiyama, N. Shimomura, K. Takasugi, T. Miyamoto, M. Sato, T. Tazima

{"title":"Gas-puff Z-pinch on pulsed power generator with self-crowbar switch","authors":"H. Akiyama, N. Shimomura, K. Takasugi, T. Miyamoto, M. Sato, T. Tazima","doi":"10.1109/PLASMA.1989.166142","DOIUrl":"https://doi.org/10.1109/PLASMA.1989.166142","url":null,"abstract":"Recent developments in pulsed power technology have increased interest in gas-puff Z-pinches as soft X-ray sources and for nuclear fusion. The pulse width of the pulsed power is extremely short, i.e. several tens of nanosecond, in comparison with the pulse width of the fast bank. Therefore, high current density is necessary to realize pinch phenomena within the pulse width. A self-crowbar switch that can be used to produce a slightly larger pulse has been proposed and tested. Experiments using the LIMAY-1 pulsed power generator are reported. The maximum stored energy, the output voltage, the pulse width, and the characteristic impedance are 13 kJ, 600 kV, 70 ns, and 3 Omega , respectively. The discharge starts at radial positions between 8 and 15 mm, after the Ar gas is injected. Then the pinch of the annular plasma occurs. The cathode and anode configurations have significant effects on the development of a homogeneous annular plasma. The discharges are grouped into four kinds of phenomena: vacuum discharges, Z-pinches without and with self-crowbar switches, and no Z-pinch with self-crowbar switches.<<ETX>>","PeriodicalId":165717,"journal":{"name":"IEEE 1989 International Conference on Plasma Science","volume":"515 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1989-12-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"132965746","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

In-vessel maintenance on the IGNITEX experiment IGNITEX实验的船内维护

IEEE 1989 International Conference on Plasma Science Pub Date : 1989-12-01 DOI: 10.1109/PLASMA.1989.166275

J. Ling, M. Barrington, R. Carrera, D. Tesar

{"title":"In-vessel maintenance on the IGNITEX experiment","authors":"J. Ling, M. Barrington, R. Carrera, D. Tesar","doi":"10.1109/PLASMA.1989.166275","DOIUrl":"https://doi.org/10.1109/PLASMA.1989.166275","url":null,"abstract":"An in-vessel remote maintenance system (IVRMS) for the IGNITEX ignition tokamak first-wall system is discussed. The design emphasizes simplicity, reliability, and low cost. Diagnostic hardware, power supplies, and fueling and vacuum systems will be located after the primary shielding so that they will be accessible for maintenance and adjustment between pulses. The essential tasks to be performed by the IVRMS are inspection of first wall and diagnostic penetrations for damage and vacuum leaks and repair of damaged areas by welding and beryllium-spray-coating techniques. Its main element is an articulated boom with nine degrees of freedom, used to position the end effectors to the desired location. Positioning of the end effectors with poloidal precision is obtained by using a guiding jig which will be deployed and attached to the first wall. The control module will be teleoperated with tach-learn capability. A self-transporting storage chamber with internal decontamination capability is envisioned. The feasibility of using frameless, lightweight, self-contained actuator modules with molded, carbon-fiber links is being studied. This design can result in a stiff articulated boom with a compact cross-sectional area suitable for use in the IGNITEX device.<<ETX>>","PeriodicalId":165717,"journal":{"name":"IEEE 1989 International Conference on Plasma Science","volume":"19 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1989-12-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"123708516","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 1

High field, single turn toroidal magnetic technology demonstration for IGNITEX IGNITEX高场单匝环形磁技术演示

IEEE 1989 International Conference on Plasma Science Pub Date : 1989-12-01 DOI: 10.1109/PLASMA.1989.166017

M. Werst, M. Driga, K. Hsieh, W. Weldon

引用次数: 0

Temperature measurements on RFP and ULQ experiments in REPUTE-1 retee -1中RFP和ULQ实验的温度测量

IEEE 1989 International Conference on Plasma Science Pub Date : 1989-12-01 DOI: 10.1109/PLASMA.1989.166067

Y. Nagayama, A. Ejiri, A. Fujisawa, T. Fujita, J. Matsui, K. Miyamoto, K. Saito, Y. Shimazu, K. Shimoji, K. Yamagishi

引用次数: 0

Experimental program for the fusion ignition experiment IGNITEX 实验程序为聚变点火实验IGNITEX

IEEE 1989 International Conference on Plasma Science Pub Date : 1989-12-01 DOI: 10.1109/PLASMA.1989.166280

R. Bickerton, W. Booth, R. Carrera, G. Fu, G. Hallock, E. Montalvo, M. Rosenbluth, J. Van Dam

{"title":"Experimental program for the fusion ignition experiment IGNITEX","authors":"R. Bickerton, W. Booth, R. Carrera, G. Fu, G. Hallock, E. Montalvo, M. Rosenbluth, J. Van Dam","doi":"10.1109/PLASMA.1989.166280","DOIUrl":"https://doi.org/10.1109/PLASMA.1989.166280","url":null,"abstract":"Computer simulations, which provide part of the scientific basis for the design of IGNITEX, show that a volume-averaged temperature of 4 keV can be reached by pure ohmic heating while remaining in stable operating regimes. These predictions are consistent with experimental results of present high-field tokamaks. The experimental program is divided into three phases covering a three year operating period. The first year, after full commissioning of the magnet, vacuum, and data systems, will be used to study plasma shape, position, and profile control and to find optimum operating regimes for the experiment using hydrogen fuel. During this phase, final calibration and refinement of the diagnostics systems will take place. During the second year deuterium fuel will be used in the experiment. Studies of isotope-ratio control will be carried out. Additionally, during these phases, scaling laws for high-density, high-temperature, ohmically heated plasmas will be studied. The first D-T experiments will be performed during the last part of the second year of operation. These will provide limited neutron and alpha production and allow final refinement of neutron and alpha diagnostics. The ignited phase of the experiment will continue throughout the third year. During this time, alpha physics experiments will be conducted.<<ETX>>","PeriodicalId":165717,"journal":{"name":"IEEE 1989 International Conference on Plasma Science","volume":"66 5","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1989-12-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"132331252","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Magnetic field effects in electrostatic analyzers used for heavy ion beam probe measurements 用于重离子束探针测量的静电分析仪中的磁场效应

IEEE 1989 International Conference on Plasma Science Pub Date : 1989-12-01 DOI: 10.1109/PLASMA.1989.166227

J. Zieliński, G. Hallock

引用次数: 0

Ion temperature in the Reversatron II RFP 反向加速器II RFP中的离子温度

IEEE 1989 International Conference on Plasma Science Pub Date : 1989-05-22 DOI: 10.1109/PLASMA.1989.166070

P. Green, S. Robertson

引用次数: 0

Propagation of high power microwave pulses in the air 高功率微波脉冲在空气中的传播

IEEE 1989 International Conference on Plasma Science Pub Date : 1989-05-22 DOI: 10.1109/PLASMA.1989.166258

S. Kuo, Y. S. Zhang

引用次数: 0

Millimeter-wave radiation generated via plasma three-wave mixing using high-current density counter-streaming electron beams 利用高电流密度逆流电子束通过等离子体三波混频产生的毫米波辐射

IEEE 1989 International Conference on Plasma Science Pub Date : 1989-05-22 DOI: 10.1109/PLASMA.1989.166239

J. Santoru, R. Schumacher

引用次数: 3