[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering最新文献_第10页

A modular timing system for megawatt gyrotrons 兆瓦级回旋管的模块化定时系统

[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-09-30 DOI: 10.1109/FUSION.1991.218717

D. Petersen

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

BPX toroidal field coil design BPX环形场线圈设计

[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-09-30 DOI: 10.1109/FUSION.1991.218880

P. Heitzenroeder

{"title":"BPX toroidal field coil design","authors":"P. Heitzenroeder","doi":"10.1109/FUSION.1991.218880","DOIUrl":"https://doi.org/10.1109/FUSION.1991.218880","url":null,"abstract":"The toroidal field coil system of the Burning Plasma Experiment (BPX) consists of 18 beryllium copper magnets arrayed in a wedged configuration with a major radius of 2.6 m and a field strength capability on axis of 9.0 T. The toroidal array is constructed from six 3-coil modules to facilitate remote recovery in the event of a magnet failure after nuclear activation precludes hands-on servicing. The magnets are of a modified Bitter plate design with partial cases of type 316-LN stainless steel welded with Inconel 182 weld wire. The coil turn plates are fabricated from CDA C17510 beryllium copper with optimized mechanical, thermal, and electrical characteristics. Cryogenic cooling is used to reduce power dissipation and to enhance performance. The magnets are cooled between experimental pulses by pressurized liquid nitrogen flowing through channels in the edges of the coil turns, allowing one full-power pulse per hour. Overturning forces are reacted by friction forces generated by the wedging pressure in the central leg regions and by case and structure in the other regions of the coil. The magnets are designed to structural design criteria modeled after the ASME Boiler and Pressure Vessel Code, Section III, but with appropriate changes.<<ETX>>","PeriodicalId":318951,"journal":{"name":"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering","volume":"30 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":"123053524","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: 2

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

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

The BPX electrical power system BPX电力系统

[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-09-30 DOI: 10.1109/FUSION.1991.218836

D. Huttar, G. Bronner, N. Fromm

{"title":"The BPX electrical power system","authors":"D. Huttar, G. Bronner, N. Fromm","doi":"10.1109/FUSION.1991.218836","DOIUrl":"https://doi.org/10.1109/FUSION.1991.218836","url":null,"abstract":"The design of the BPX (Burning Plasma Experiment) power system has evolved over a period of several years and has included studies of several alternative approaches. The reapplication of the existing TFTR (Tokamak Fusion Test Reactor) power and energy facilities has been basic to all approaches. The dynamics of the power requirements for the BPX poloidal coil system suggest that the TFTR facilities would be most suitably applied to that requirement. The chief concern related to that match has been the adequacy of the 4.5-GJ energy rating of the TFTR flywheel units. The toroidal field power requirements are the greatest of the BPX subsystems and, fortunately, are sufficiently free of dynamics to allow the consideration of different approaches to providing pulse power and energy. Additional design challenges were presented by the multiplicity of plasma control scenarios incorporated in the BPX physics planning and the power response demanded of the plasma position control system. The plasma control scenarios include upper, lower, and symmetrical poloidal diverter operation as well as limiter operation. The plasma position control coils (internal to the TF bore) have a collective peak power demand of 640 MVA, require four quadrant drive, and require 1 ms voltage response.<<ETX>>","PeriodicalId":318951,"journal":{"name":"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering","volume":"58 10","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1991-09-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"132870926","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

Implications of ENDF/B-VI beryllium data on the performance of the reference ARIES-I blanket ENDF/B-VI铍数据对参考ARIES-I毛毯性能的影响

[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-09-30 DOI: 10.1109/FUSION.1991.218779

S. Pelloni, E. Cheng

引用次数: 0

Poloidal field (PF) coil system design and R&D for the Burning Plasma Experiment (BPX) 燃烧等离子体实验用极向场(PF)线圈系统的设计与研发

[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-09-30 DOI: 10.1109/FUSION.1991.218879

R. Thome, B.A. Smith, R. Pillsbury, P. Titus, R. Myatt

引用次数: 0

Mechanical design and analysis of JT-60U ICRF launcher JT-60U型ICRF发射装置的力学设计与分析

[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-09-30 DOI: 10.1109/FUSION.1991.218814

T. Fujii, M. Saigusa, S. Moriyama, K. Annoh, S. Shinozaki, M. Terakado, H. Kimura, M. Ohta, M. Texuka, K. Wakabayashi, J. Ohmori, N. Miki, N. Kobayashi, K. Itoh

引用次数: 2