[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering最新文献_第9页

Experimental high heat load surface damage of graphite and refractory materials 高热负荷对石墨和耐火材料表面损伤的实验研究

[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-09-30 DOI: 10.1109/FUSION.1991.218799

M. Bourham, O. Hankins, W. Eddy, J. Hurley, J. Earnhart, J. Gilligan

引用次数: 1

JT-60 operation results after its modification for higher plasma current with single null open divertor JT-60单空开导流器改造后的运行结果

[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-09-30 DOI: 10.1109/FUSION.1991.218923

I. Kondo, H. Horiike, Y. Neyatani, M. Matsukawa, T. Ando, R. Yoshino, T. Arai, H. Ninomiya, M. Yamamoto, T. Koike, K. Kodama, K. Miyachi, M. Honda, H. Hiratsuka

引用次数: 2

Beryllium safety at JET 铍在JET的安全性

[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-09-30 DOI: 10.1109/FUSION.1991.218850

R. Russ, A. Haigh, S. J. Booth

引用次数: 4

Signal conditioning electronics and packaging for the Alcator C-MOD tokamak 阿尔卡托C-MOD托卡马克的信号调理电子和封装

[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-09-30 DOI: 10.1109/FUSION.1991.218729

W. Parkin

{"title":"Signal conditioning electronics and packaging for the Alcator C-MOD tokamak","authors":"W. Parkin","doi":"10.1109/FUSION.1991.218729","DOIUrl":"https://doi.org/10.1109/FUSION.1991.218729","url":null,"abstract":"A design utilizing industry-standard EURO card packaging, connected via ribbon cable to a custom I/O backplane, accommodates the many different circuits to be used on Alcator C-MOD. The chassis approach eliminates packaging, powering, and mounting problems associated with one-of-a-kind circuits and allows dense packaging of multiple circuits. The separate I/O backplane allows easy removal and replacement of circuit cards, while leaving front panel space available for circuit-specific indicators. The DIN pin-and-socket connectors are considerably more robust and reliable than edge connectors. The pin-out allows up to four circuits per card, allowing up to eighty channels in one 5-1/2-in-tall, rack mountable chassis. A variety of general-purpose signal conditioning circuit cards was designed and built for engineering and diagnostic systems. Four channel circuits include low-drift integrators, analog multiplexers, temperature controllers, instrumentation amplifiers, transimpedance amplifiers, and an eight-pole Bessel filter for anti-aliasing applications. A two-channel card provides thermal electric cooler control. Fiber-optic interface is provided by an 8-b digital transceiver and an analog fiber-optic link.<<ETX>>","PeriodicalId":318951,"journal":{"name":"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering","volume":"176 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1991-09-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"121927994","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: 3

High power (22 MW) ICRH at JET and developments for next step devices JET的高功率(22兆瓦)ICRH和下一步设备的开发

[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-09-30 DOI: 10.1109/FUSION.1991.218703

T. Wade, J. Jacquinot, G. Bosia, A. Sibley, M. Schmid

引用次数: 6

ICRH Thomson tetrodes: from long pulses to CW ICRH汤姆逊四极:从长脉冲到连续波

[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-09-30 DOI: 10.1109/FUSION.1991.218876

G. Clerc, J.P. Ichac, M. Tardy

{"title":"ICRH Thomson tetrodes: from long pulses to CW","authors":"G. Clerc, J.P. Ichac, M. Tardy","doi":"10.1109/FUSION.1991.218876","DOIUrl":"https://doi.org/10.1109/FUSION.1991.218876","url":null,"abstract":"Thomson Tubes Electroniques tetrodes of the 2 MW class, the TH 525 and the TH 526, have now entered the industrial production line, and their amplifiers are fully operational. They have already made it possible to reach outstanding results on plasmas. At JET (Joint European Torus), 16 amplifiers (25-27 MHz) are fitted with TH 525 tetrodes, which each deliver 2 MW of RF power in 20 s pulses to a plasma load (voltage standing wave ratio up to 1.5:1). The JET teams have tested these tubes up to 2.7 MW peak. A record peak of 22.5 MW of ICRH (ion cyclotron resonance heating) power has been coupled to the plasma (26.3 MW at the amplifier output). Two TH 525 tetrodes have also delivered their RF power to the TEXTOR plasma for more than two years. Six generators with TH 526 tetrodes are also delivering 2 MW each during 30 s, between 35 and 80 MHz, at TORE SUPRA. They have also been tested with the same pulse length at 1.4 MW/120 MHz, and are operational at 1 MW at this frequency, with high figures of gain, bandwidth, and efficiency. The next generation of Thomson tetrodes will make it possible to reach the same levels of power at these frequencies in CW (continuous wave) operation, with an even higher efficiency.<<ETX>>","PeriodicalId":318951,"journal":{"name":"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering","volume":"1 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1991-09-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"126725057","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: 7

Design of ICRF antennas for TFTR TFTR中ICRF天线的设计

[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-09-30 DOI: 10.1109/FUSION.1991.218939

S. Raftopoulos, R. Scillia, P. Bonanos, J. Hosea, J. Wilson, W. Enoch

{"title":"Design of ICRF antennas for TFTR","authors":"S. Raftopoulos, R. Scillia, P. Bonanos, J. Hosea, J. Wilson, W. Enoch","doi":"10.1109/FUSION.1991.218939","DOIUrl":"https://doi.org/10.1109/FUSION.1991.218939","url":null,"abstract":"Two 4-MW ICRF (ion cyclotron range of frequencies) antennas have been designed for the Tokamak Fusion Test Reactor (TFTR). The antennas will be installed adjacent to the two existing antennas, bringing the maximum ICRF heating capacity to 12.5 MW. The design goals were to increase the loading to the plasma, to reduce the tendency for arcing, and to simplify the fabrication and assembly of the device. The antenna, consisting of an RF cavity with slots at the front end (facing the plasma), utilizes a center-mounted spline drive mechanism for positioning the device with respect to the plasma edge and for resisting the forces generated during disruptions. The Faraday shields are unique for each launcher, though they share common design elements. Both launchers use solid Inconel rods that are bent to a radius matching the plasma and tilted six degrees in order to be parallel with the combined poloidal and toroidal fields of the tokamak. The 'Bay K' launcher uses a single row shield while the 'Bay N' launcher incorporates a double row shield. Faraday shield protection and the center-grounded current straps are also discussed.<<ETX>>","PeriodicalId":318951,"journal":{"name":"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering","volume":"1 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1991-09-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"128957258","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

SF/sub 6/ and water cold trap for TFTR deuterium-tritium operations SF/ sub6 /和水冷阱用于TFTR氘-氚操作

[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-09-30 DOI: 10.1109/FUSION.1991.218777

M. Viola, L. Dudek, V. Garzotto, J. Kamperschroer, G. Martin, R. Rossmassler, R. Sissingh

{"title":"SF/sub 6/ and water cold trap for TFTR deuterium-tritium operations","authors":"M. Viola, L. Dudek, V. Garzotto, J. Kamperschroer, G. Martin, R. Rossmassler, R. Sissingh","doi":"10.1109/FUSION.1991.218777","DOIUrl":"https://doi.org/10.1109/FUSION.1991.218777","url":null,"abstract":"The Tokamak Fusion Test Reactor (TFTR) vacuum system is being upgraded to trap SF/sub 6/ gas which may leak from the neutral beam injectors during the planned deuterium-tritium experiments. This is necessary since SF/sub 6/ can, in 25% of a gram-mole, completely inactivate the platinum catalyst in the tritium cleanup system (TCS). Any SF/sub 6/ leaking into the injectors will initially be held on the liquid helium or liquid nitrogen cryopanels. During regens of the liquid helium panel, the deuterium and tritium will pass to the TCS, with the SF/sub 6/ being retained on the cryopanels. In the final phase of the accident recovery scenario, the cryopanels will be warmed to room temperature and the SF/sub 6/ collected by a liquid-nitrogen cooled cold trap. Design of the cold trap and measurements of the vapor pressure of SF/sub 6/ at 77 K as a function of surface coverage are presented. The SF/sub 6/ vapor pressure at 77 K, with only a few monolayers absorbed, was found to be <10/sup -7/ torr. Modest pressures of approximately 10/sup -5/ torr were measured after nearly 3*10/sup 5/ torr-1 were deposited on a cold trap with an area of 0.1 m/sup 2/. In the final configuration, the cold trap will also be used to collect water which may have accidentally leaked into the vacuum system.<<ETX>>","PeriodicalId":318951,"journal":{"name":"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering","volume":"04 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1991-09-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"127184965","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

Monte-Carlo studies of radiation damage by fusion neutron in the first wall 第一壁核聚变中子辐射损伤的蒙特卡罗研究

[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-09-30 DOI: 10.1109/FUSION.1991.218688

X. Gao, Y. Hou, Z. Pan, Q.Y. Shao, J.X. Chen, S.M. Wu

引用次数: 0

Variable-speed constant-frequency AC generator with flywheel for power supply system of the fusion facility 核聚变设施供电系统用飞轮变速恒频交流发电机

[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-09-30 DOI: 10.1109/FUSION.1991.218864

H. Chikaraishi, H. Kihara, R. Shimada

引用次数: 1