Pub Date : 1993-10-11DOI: 10.1109/FUSION.1993.518377
R. Uhlemann, H. Reimer, M. Lochter
Neutral particle beams of the /sup 3/He isotope in the megawatt range were successfully produced by the neutral beam injectors of TEXTOR. Measurements of beam and ion source characterizing data, i.e. perveance, divergence, neutralization efficiency, beamline transmission and gas flow rates for 50 kV, 49 A, 2.5 MW, 3 sec /sup 3/He beams are compared with relevant data of hydrogen, deuterium and /sup 4/He. The LHe cryo condensation pumps are capable of pumping the resulting /sup 3/He gas flow rates of 50 mbl/s without technical modification at 4.2 K, if covered prior to each beam pulse by an amount of argon frost with proper ratio of Ar/He. Beamline pressure, reionization losses and preliminary results of /sup 3/He-injection into TEXTOR are given.
{"title":"/sup 3/He high power neutral beams for TEXTOR comparison of 55 KeV particle beam and vacuum system data with /sup 4/He, deuterium and hydrogen","authors":"R. Uhlemann, H. Reimer, M. Lochter","doi":"10.1109/FUSION.1993.518377","DOIUrl":"https://doi.org/10.1109/FUSION.1993.518377","url":null,"abstract":"Neutral particle beams of the /sup 3/He isotope in the megawatt range were successfully produced by the neutral beam injectors of TEXTOR. Measurements of beam and ion source characterizing data, i.e. perveance, divergence, neutralization efficiency, beamline transmission and gas flow rates for 50 kV, 49 A, 2.5 MW, 3 sec /sup 3/He beams are compared with relevant data of hydrogen, deuterium and /sup 4/He. The LHe cryo condensation pumps are capable of pumping the resulting /sup 3/He gas flow rates of 50 mbl/s without technical modification at 4.2 K, if covered prior to each beam pulse by an amount of argon frost with proper ratio of Ar/He. Beamline pressure, reionization losses and preliminary results of /sup 3/He-injection into TEXTOR are given.","PeriodicalId":365814,"journal":{"name":"15th IEEE/NPSS Symposium. Fusion Engineering","volume":"42 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1993-10-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"131873185","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}
Pub Date : 1993-10-11DOI: 10.1109/FUSION.1993.518369
R. Hong
DIII-D neutral beam ion sources are operated in the emission limited arc discharge regime. Filament temperature has been observed to play an important role in the ion source operation. Effects of the filament temperature on the arc discharge efficiency (Langmuir probe signal of the arc discharge/arc power) and arc efficiency (extracted beam current/arc power) have been experimentally measured. The results show that both efficiencies reach optimum values with respect to filament temperature. The optimum arc efficiency is independent of the beam energy, but the filament temperature at which optimum arc efficiency is obtained shifts to higher values with higher beam energy. Gas puff into the neutralizer is necessary to achieve optimum neutralization efficiency, but it also increases both particle collisions in the accelerator column and gas flow into the arc chamber. Tests show that arc efficiency decreases only slightly with increasing particle collisions, since loss in the extracted beam current is compensated for by the decreasing we power required to sustain the arc discharge with additional gas flow. The most significant effect of particle collisions is the sharp increase of the gradient grid current, which can cause damage to the grid.
{"title":"Efficiency of arc discharge and beam extraction of the DIII-D neutral beam ion source","authors":"R. Hong","doi":"10.1109/FUSION.1993.518369","DOIUrl":"https://doi.org/10.1109/FUSION.1993.518369","url":null,"abstract":"DIII-D neutral beam ion sources are operated in the emission limited arc discharge regime. Filament temperature has been observed to play an important role in the ion source operation. Effects of the filament temperature on the arc discharge efficiency (Langmuir probe signal of the arc discharge/arc power) and arc efficiency (extracted beam current/arc power) have been experimentally measured. The results show that both efficiencies reach optimum values with respect to filament temperature. The optimum arc efficiency is independent of the beam energy, but the filament temperature at which optimum arc efficiency is obtained shifts to higher values with higher beam energy. Gas puff into the neutralizer is necessary to achieve optimum neutralization efficiency, but it also increases both particle collisions in the accelerator column and gas flow into the arc chamber. Tests show that arc efficiency decreases only slightly with increasing particle collisions, since loss in the extracted beam current is compensated for by the decreasing we power required to sustain the arc discharge with additional gas flow. The most significant effect of particle collisions is the sharp increase of the gradient grid current, which can cause damage to the grid.","PeriodicalId":365814,"journal":{"name":"15th IEEE/NPSS Symposium. Fusion Engineering","volume":"173 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1993-10-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"133277515","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}
Pub Date : 1993-10-11DOI: 10.1109/FUSION.1993.518301
T. Gibney, D. Greenwood
Recent years have see an upsurge in inter-laboratory collaboration within the fusion community. Also, increasingly powerful and inexpensive workstations, linked together by Local Area Networks and through the Internet, have become available for data analysis. It has therefore become essential to provide a mechanism for getting data from a central facility computer to application programs running on a diverse assortment of workstations and larger computers, both locally and at remote sites. The Data Server (DS) protocol defines a client/server communication standard to help satisfy this need. The protocol, a joint development project between PPPL and ORNL, was designed specifically to handle the type of experimental data (separate shot numbers, diagnostic specific) generated by the fusion energy community. It provides a flexible, machine-independent standard for network access to remotely stored data. Subroutines within the local data-access library, while retaining the same outward appearance, are modified to include client code for network data access. Through normal library calls, a user application transparently connects with an experiment-specific Server via TCP/IP over a Local Area Network or through the Internet. The server program presents its local data to the network client following protocol standards. By simple, well-defined request/reply transactions, the client (library routine) gets the information necessary for its normal operation. The network communication is entirely hidden from the user.
{"title":"DS data server: sharing fusion-energy data and results","authors":"T. Gibney, D. Greenwood","doi":"10.1109/FUSION.1993.518301","DOIUrl":"https://doi.org/10.1109/FUSION.1993.518301","url":null,"abstract":"Recent years have see an upsurge in inter-laboratory collaboration within the fusion community. Also, increasingly powerful and inexpensive workstations, linked together by Local Area Networks and through the Internet, have become available for data analysis. It has therefore become essential to provide a mechanism for getting data from a central facility computer to application programs running on a diverse assortment of workstations and larger computers, both locally and at remote sites. The Data Server (DS) protocol defines a client/server communication standard to help satisfy this need. The protocol, a joint development project between PPPL and ORNL, was designed specifically to handle the type of experimental data (separate shot numbers, diagnostic specific) generated by the fusion energy community. It provides a flexible, machine-independent standard for network access to remotely stored data. Subroutines within the local data-access library, while retaining the same outward appearance, are modified to include client code for network data access. Through normal library calls, a user application transparently connects with an experiment-specific Server via TCP/IP over a Local Area Network or through the Internet. The server program presents its local data to the network client following protocol standards. By simple, well-defined request/reply transactions, the client (library routine) gets the information necessary for its normal operation. The network communication is entirely hidden from the user.","PeriodicalId":365814,"journal":{"name":"15th IEEE/NPSS Symposium. Fusion Engineering","volume":"5 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1993-10-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"131689098","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}
Pub Date : 1993-10-11DOI: 10.1109/FUSION.1993.518395
J. J. Harris, G. Campbell
A centralized graphical user interface has been added to the DIII-D neutral beam (NB) control systems for status monitoring and remote control applications. This user interface provides for automatic data acquisition, alarm detection and supervisory control of the four NB programmable logic controllers (PLC) as well as the mode control PLC. These PLCs are used for interlocking, control and status of the NB vacuum pumping, gas delivery, and water cooling systems as well as beam mode status and control. The system allows for both a friendly user interface as well as a safe and convenient method of communicating with remote hardware that formerly required interruption of machine operations to access. In the future, to enable high level of control of PLC subsystems, complete procedures can be written and executed at the touch of a screen control panel button. The system consists of an IBM compatible 486 computer running the FIX DMACS for Windows data acquisition and control operator interface software, a Texas Instruments/Siemens communication card and Phoenix Digital optical communications modules. Communication is achieved via the TIWAY (Texas Instruments) protocol link utilizing both fiber optic communications and a copper local area network (LAN). Hardware and software capabilities will be reviewed. Data and alarm reporting, extended monitoring and control capabilities will also be discussed.
集中式图形用户界面已添加到DIII-D中性波束(NB)控制系统中，用于状态监测和远程控制应用。该用户界面提供了四个NB可编程逻辑控制器(PLC)的自动数据采集、报警检测和监控以及PLC的模式控制。这些plc用于联锁，控制和NB真空泵，气体输送和水冷却系统的状态，以及光束模式的状态和控制。该系统既允许一个友好的用户界面，也允许一种安全方便的方法与以前需要中断机器操作才能访问的远程硬件进行通信。将来，为了实现PLC子系统的高水平控制，可以通过触摸屏幕控制面板按钮来编写和执行完整的程序。该系统由一台运行FIX DMACS for Windows数据采集和控制操作界面软件的IBM兼容486计算机、一张德州仪器/西门子通信卡和Phoenix数字光通信模块组成。通信通过TIWAY(德州仪器)协议链路实现，利用光纤通信和铜局域网(LAN)。将审查硬件和软件能力。数据和报警报告，扩展的监测和控制能力也将被讨论。
{"title":"DIII-D neutral beam control system operator interface","authors":"J. J. Harris, G. Campbell","doi":"10.1109/FUSION.1993.518395","DOIUrl":"https://doi.org/10.1109/FUSION.1993.518395","url":null,"abstract":"A centralized graphical user interface has been added to the DIII-D neutral beam (NB) control systems for status monitoring and remote control applications. This user interface provides for automatic data acquisition, alarm detection and supervisory control of the four NB programmable logic controllers (PLC) as well as the mode control PLC. These PLCs are used for interlocking, control and status of the NB vacuum pumping, gas delivery, and water cooling systems as well as beam mode status and control. The system allows for both a friendly user interface as well as a safe and convenient method of communicating with remote hardware that formerly required interruption of machine operations to access. In the future, to enable high level of control of PLC subsystems, complete procedures can be written and executed at the touch of a screen control panel button. The system consists of an IBM compatible 486 computer running the FIX DMACS for Windows data acquisition and control operator interface software, a Texas Instruments/Siemens communication card and Phoenix Digital optical communications modules. Communication is achieved via the TIWAY (Texas Instruments) protocol link utilizing both fiber optic communications and a copper local area network (LAN). Hardware and software capabilities will be reviewed. Data and alarm reporting, extended monitoring and control capabilities will also be discussed.","PeriodicalId":365814,"journal":{"name":"15th IEEE/NPSS Symposium. Fusion Engineering","volume":"221 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1993-10-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"132180640","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}
Pub Date : 1993-10-11DOI: 10.1109/FUSION.1993.518383
Y. Feldshteyn, S. Dinkevich, Ș. Stoenescu, J. Warren
The Tokamak Physics Experiment (TPX) machine is a compact steady state fusion device. The TPX vacuum vessel provides the vacuum boundary for the plasma and mechanical support for internal components. The vacuum vessel itself and internal components are subjected to large heat loads during bakeout and plasma operation. A dual function heating/cooling system has been designed to satisfy thermal requirements for the vacuum vessel and in-vessel components. A successful Conceptual Design Review (CDR) was held in March 1993. Important parameters presented at the CDR are described herein.
{"title":"TPX vacuum vessel heating and cooling system","authors":"Y. Feldshteyn, S. Dinkevich, Ș. Stoenescu, J. Warren","doi":"10.1109/FUSION.1993.518383","DOIUrl":"https://doi.org/10.1109/FUSION.1993.518383","url":null,"abstract":"The Tokamak Physics Experiment (TPX) machine is a compact steady state fusion device. The TPX vacuum vessel provides the vacuum boundary for the plasma and mechanical support for internal components. The vacuum vessel itself and internal components are subjected to large heat loads during bakeout and plasma operation. A dual function heating/cooling system has been designed to satisfy thermal requirements for the vacuum vessel and in-vessel components. A successful Conceptual Design Review (CDR) was held in March 1993. Important parameters presented at the CDR are described herein.","PeriodicalId":365814,"journal":{"name":"15th IEEE/NPSS Symposium. Fusion Engineering","volume":"47 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1993-10-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"133897536","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}
Pub Date : 1993-10-11DOI: 10.1109/FUSION.1993.518300
W. Stark, V.J. Abraitis, S. Davis, R. Simmons, S.M. Young, C. Flanagan
The Tokamak Physics Experiment (TPX) and the International Thermonuclear Engineering Reactor (ITER) are the major national design efforts currently underway by the US fusion program. These design efforts are being performed at many different sites consisting of national laboratories, universities, and industrial partners. This paper presents the current status of work in support of expediting communication and enhancing the collaborative process by providing a framework of common tools and resources for all collaborators. The key components of this framework are common applications which support desktop mail, directory services, and convenient desktop access to project design documents. A discussion of the issues associated with the deployment, support, and future evolution of this framework will be presented.
{"title":"Tools and frameworks supporting TPX and ITER design collaborations","authors":"W. Stark, V.J. Abraitis, S. Davis, R. Simmons, S.M. Young, C. Flanagan","doi":"10.1109/FUSION.1993.518300","DOIUrl":"https://doi.org/10.1109/FUSION.1993.518300","url":null,"abstract":"The Tokamak Physics Experiment (TPX) and the International Thermonuclear Engineering Reactor (ITER) are the major national design efforts currently underway by the US fusion program. These design efforts are being performed at many different sites consisting of national laboratories, universities, and industrial partners. This paper presents the current status of work in support of expediting communication and enhancing the collaborative process by providing a framework of common tools and resources for all collaborators. The key components of this framework are common applications which support desktop mail, directory services, and convenient desktop access to project design documents. A discussion of the issues associated with the deployment, support, and future evolution of this framework will be presented.","PeriodicalId":365814,"journal":{"name":"15th IEEE/NPSS Symposium. Fusion Engineering","volume":"214 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1993-10-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"121237662","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}
Pub Date : 1993-10-11DOI: 10.1109/FUSION.1993.518359
M. Nishi, H. Nakajima, T. Ando, T. Hiyama, Y. Takahashi, K. Okuno, K. Yoshida, T. Kato, K. Kawano, T. Isono, M. Sugimoto, N. Koizumi, K. Hamada, T. Sasaki, K. Imahashi, S. Iwamoto, H. Ebisu, T. Ouchi, K. Ohtsu, J. Okayama, M. Oshikiri, T. Kawasaki, S. Seki, S. Sekiguchi, T. Takahashi, Y. Takaya, F. Tajiri, H. Tsukamoto, H. Hanawa, F. Hosono, A. Miyake, Y. Yasukawa, K. Yamamoto, H. Wakabayashi, Y. Wadayama, H. Tsuji
As a high-field pulse-poloidal test coil in the development program of superconducting coils for fusion machines, a 1 m-inner diameter superconducting coil named DPC-EX wound with 10 kA Nb/sub 3/Sn cable-in-conduit forced-cooled conductor was fabricated and its various performances were investigated. In its second test, the ramp-rate limitation phenomenon, i.e. the dependence of the coil current at quench on the current ramp speed, was studied in detail and a lot of important data for the design of large pulse coils were achieved.
作为核聚变用超导线圈研制计划中的高场脉冲极向试验线圈，采用10 kA Nb/sub - 3/Sn管内强制冷却导线绕制了内径为1 m的超导线圈DPC-EX，并对其各项性能进行了研究。在第二次试验中，详细研究了缓变速率限制现象，即线圈在猝灭时电流对电流缓变速率的依赖关系，获得了许多大脉冲线圈设计的重要数据。
{"title":"Ramp-rate limitation test results of the Nb/sub 3/Sn Demo Poloidal Coil (DPC-EX)","authors":"M. Nishi, H. Nakajima, T. Ando, T. Hiyama, Y. Takahashi, K. Okuno, K. Yoshida, T. Kato, K. Kawano, T. Isono, M. Sugimoto, N. Koizumi, K. Hamada, T. Sasaki, K. Imahashi, S. Iwamoto, H. Ebisu, T. Ouchi, K. Ohtsu, J. Okayama, M. Oshikiri, T. Kawasaki, S. Seki, S. Sekiguchi, T. Takahashi, Y. Takaya, F. Tajiri, H. Tsukamoto, H. Hanawa, F. Hosono, A. Miyake, Y. Yasukawa, K. Yamamoto, H. Wakabayashi, Y. Wadayama, H. Tsuji","doi":"10.1109/FUSION.1993.518359","DOIUrl":"https://doi.org/10.1109/FUSION.1993.518359","url":null,"abstract":"As a high-field pulse-poloidal test coil in the development program of superconducting coils for fusion machines, a 1 m-inner diameter superconducting coil named DPC-EX wound with 10 kA Nb/sub 3/Sn cable-in-conduit forced-cooled conductor was fabricated and its various performances were investigated. In its second test, the ramp-rate limitation phenomenon, i.e. the dependence of the coil current at quench on the current ramp speed, was studied in detail and a lot of important data for the design of large pulse coils were achieved.","PeriodicalId":365814,"journal":{"name":"15th IEEE/NPSS Symposium. Fusion Engineering","volume":"31 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1993-10-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"125387909","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}
Pub Date : 1993-10-11DOI: 10.1109/FUSION.1993.518290
A. Cosler, E. Kemmereit, H. Soltwisch
A combined HCN laser interferometer/polarimeter comprising nine vertical probing beams has been in routine use on TEXTOR for simultaneous measurements of the electron density and poloidal magnetic field distributions and for feedback control of the gas injection and horizontal plasma positioning systems. Motivated by a growing interest in rapid changes of the internal magnetic field structure as well as by the need for reliable control diagnostics of the plasma shape and vertical position under long pulse conditions, the instrument has been complemented recently with a horizontal channel. The upgrading has been achieved by minor modifications of the existing optical arrangement and mechanical structure without impairing the function of the original apparatus. In this contribution, the constraints and technical solutions for the alterations are outlined and the improved performance is illustrated by practical examples.
{"title":"Upgrade of the far-infrared interferometer and polarimeter on TEXTOR","authors":"A. Cosler, E. Kemmereit, H. Soltwisch","doi":"10.1109/FUSION.1993.518290","DOIUrl":"https://doi.org/10.1109/FUSION.1993.518290","url":null,"abstract":"A combined HCN laser interferometer/polarimeter comprising nine vertical probing beams has been in routine use on TEXTOR for simultaneous measurements of the electron density and poloidal magnetic field distributions and for feedback control of the gas injection and horizontal plasma positioning systems. Motivated by a growing interest in rapid changes of the internal magnetic field structure as well as by the need for reliable control diagnostics of the plasma shape and vertical position under long pulse conditions, the instrument has been complemented recently with a horizontal channel. The upgrading has been achieved by minor modifications of the existing optical arrangement and mechanical structure without impairing the function of the original apparatus. In this contribution, the constraints and technical solutions for the alterations are outlined and the improved performance is illustrated by practical examples.","PeriodicalId":365814,"journal":{"name":"15th IEEE/NPSS Symposium. Fusion Engineering","volume":"19 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1993-10-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"121639417","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}
Pub Date : 1993-10-11DOI: 10.1109/FUSION.1993.518527
I. Anashkin, V.V. Asmalovksy, A. N. Vertiporokh, D. Ivanov, I. A. Posadsky, P. Khvostenko
The paper is devoted to the experimental results obtained in 1992-1993 on the T-15 superconducting toroidal field coil with a stored energy of 380 MJ using Nb/sub 3/Sn. The critical current dependence on the temperature in the range T/sub in/=4.5-12 K was obtained. The current 4.0 kA was achieved, which corresponds to a magnetic field at the axis of 3.6 T and a peak field at the conductor of 6.5 T. The level of the resistive heat load versus transport current was studied-Q/sub res/ achieves 300 W at 3.6 kA. It was shown that plasma current disruptions with a rate up to 80 MA/s did not affect the coil stability.
{"title":"Status and test results of the Tokamak-15 superconducting toroidal field coil","authors":"I. Anashkin, V.V. Asmalovksy, A. N. Vertiporokh, D. Ivanov, I. A. Posadsky, P. Khvostenko","doi":"10.1109/FUSION.1993.518527","DOIUrl":"https://doi.org/10.1109/FUSION.1993.518527","url":null,"abstract":"The paper is devoted to the experimental results obtained in 1992-1993 on the T-15 superconducting toroidal field coil with a stored energy of 380 MJ using Nb/sub 3/Sn. The critical current dependence on the temperature in the range T/sub in/=4.5-12 K was obtained. The current 4.0 kA was achieved, which corresponds to a magnetic field at the axis of 3.6 T and a peak field at the conductor of 6.5 T. The level of the resistive heat load versus transport current was studied-Q/sub res/ achieves 300 W at 3.6 kA. It was shown that plasma current disruptions with a rate up to 80 MA/s did not affect the coil stability.","PeriodicalId":365814,"journal":{"name":"15th IEEE/NPSS Symposium. Fusion Engineering","volume":"29 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1993-10-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"129356391","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}
Pub Date : 1993-10-11DOI: 10.1109/FUSION.1993.518456
H.C. Mantz, D. Bowers, J. Haines, F. Williams
Poloidal limiters are required on the Tokamak Physics Experiment (TPX) for startup and to provide protection to the RF antennas. This paper discusses the conceptual design of these limiters and the analyses associated with the design. The configuration of the limiters is described and includes the carbon-carbon (C-C) tile design and their attachment concept. The thermal response of the limiters to startup and steady state plasma conditions is discussed. The required water coolant flow rates and resulting pressure drops are presented. The structural response of the limiter to both halo and eddy current disruption conditions is also included.
{"title":"TPX poloidal limiter design","authors":"H.C. Mantz, D. Bowers, J. Haines, F. Williams","doi":"10.1109/FUSION.1993.518456","DOIUrl":"https://doi.org/10.1109/FUSION.1993.518456","url":null,"abstract":"Poloidal limiters are required on the Tokamak Physics Experiment (TPX) for startup and to provide protection to the RF antennas. This paper discusses the conceptual design of these limiters and the analyses associated with the design. The configuration of the limiters is described and includes the carbon-carbon (C-C) tile design and their attachment concept. The thermal response of the limiters to startup and steady state plasma conditions is discussed. The required water coolant flow rates and resulting pressure drops are presented. The structural response of the limiter to both halo and eddy current disruption conditions is also included.","PeriodicalId":365814,"journal":{"name":"15th IEEE/NPSS Symposium. Fusion Engineering","volume":"68 4 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1993-10-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"128173098","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}
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