Pub Date : 1993-10-11DOI: 10.1109/FUSION.1993.518319
P. Campostrini, M. Fauri, G. Marchiori, P. Sonato, S. Vitturi, G. Zollino
The vacuum vessel of RFX has been designed to operate between room temperature and 350/spl deg/C during experimental sessions and during first wall conditioning operations. The temperature control system of the vacuum vessel consists of the measurement and the heating systems, connected to the RFX central control system, SIGMA. The data acquisition electronics supplies the temperature signals to the heating system and to SIGMA. The heating system provides uniform heating in both toroidal and poloidal directions. SIGMA allows different modes of operation and handles the alarm signals. After a description of the main components, the results of the first two years of operation are presented.
{"title":"Control of the vacuum vessel temperature in RFX","authors":"P. Campostrini, M. Fauri, G. Marchiori, P. Sonato, S. Vitturi, G. Zollino","doi":"10.1109/FUSION.1993.518319","DOIUrl":"https://doi.org/10.1109/FUSION.1993.518319","url":null,"abstract":"The vacuum vessel of RFX has been designed to operate between room temperature and 350/spl deg/C during experimental sessions and during first wall conditioning operations. The temperature control system of the vacuum vessel consists of the measurement and the heating systems, connected to the RFX central control system, SIGMA. The data acquisition electronics supplies the temperature signals to the heating system and to SIGMA. The heating system provides uniform heating in both toroidal and poloidal directions. SIGMA allows different modes of operation and handles the alarm signals. After a description of the main components, the results of the first two years of operation are presented.","PeriodicalId":365814,"journal":{"name":"15th IEEE/NPSS Symposium. Fusion Engineering","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"1993-10-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"115491815","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.1993.518298
P.A. Henline
For the past several years, it has been evident that the very old MODCOMP 18-bit computers being used at DIII-D for control and data acquisition were no longer adequate to perform the services needed. In early 1992, the computer systems group began to look seriously into alternate systems to replace these aged MODCOMP systems. The decision was made to investigate 'OPEN' system computers and also to maintain the compatibility with our large usage of CAMAC equipment as the real-time hardware interface. Information about the needs for real-time capabilities and 'OPEN' systems ability to meet these needs will be discussed. The needs include hardware requirements, operating system software which has known response rates, interconnectability and access of data from other workstations and computers. Some of the parameters and pitfalls of open systems will be discussed as well as the advantages of OPEN systems for use in a real-time environment. Our success at arriving at an OPEN systems solution will be examined.
{"title":"Use of OPEN systems for control, analysis and data acquisition of the DIII-D tokamak","authors":"P.A. Henline","doi":"10.1109/FUSION.1993.518298","DOIUrl":"https://doi.org/10.1109/FUSION.1993.518298","url":null,"abstract":"For the past several years, it has been evident that the very old MODCOMP 18-bit computers being used at DIII-D for control and data acquisition were no longer adequate to perform the services needed. In early 1992, the computer systems group began to look seriously into alternate systems to replace these aged MODCOMP systems. The decision was made to investigate 'OPEN' system computers and also to maintain the compatibility with our large usage of CAMAC equipment as the real-time hardware interface. Information about the needs for real-time capabilities and 'OPEN' systems ability to meet these needs will be discussed. The needs include hardware requirements, operating system software which has known response rates, interconnectability and access of data from other workstations and computers. Some of the parameters and pitfalls of open systems will be discussed as well as the advantages of OPEN systems for use in a real-time environment. Our success at arriving at an OPEN systems solution will be examined.","PeriodicalId":365814,"journal":{"name":"15th IEEE/NPSS Symposium. Fusion Engineering","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"1993-10-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"122426613","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.1993.518342
G. Barnes, G. R. Walton, D. Bashore
The Tokamak Fusion Test Reactor (TFTR) at the Princeton Plasma Physics Laboratory (PPPL) employs Toroidal Field (TF) and Poloidal Field (PF) coils to generate the magnetic fields required for fusion plasma confinement. Several small deionized cooling water leaks in several TF coils had occurred and impacted TFTR operations. In order to prepare the TF coils for D-T experimental runs, the TF coil's deionized water coolant was replaced with a dielectric fluid-perfluoroheptane (3M Fluorinert PF-5070) in May 1993. The TF Alternate Cooling System (Fluorinert) is now in the operational phase. This paper describes how the TF Alternate Cooling System (Fluorinert) is operationally different from its predecessor (water) and how the Water Systems Group participated in the testing of the system. Operations and the special techniques that the TF Alternate Cooling System requires for maintenance are a part of this paper. The training of the Water Systems personnel in order to effectively monitor the controls and equipment for Fluorinert cooling during tritium operations is also addressed. This paper also describes the application of commercially available hardware and software to mitigate the consequences of a coil cooling flow loss. The TFTR Coil Flowswitch Monitoring System is devoted to coil protection and employs a programmable logic controller (PLC) to monitor the cooling flow at the outlet of each coil's cooling path. The system inhibits field coil rectifier operation when failure conditions exist and employs various redundant and stuck mode features. The Coil Flowswitch Monitoring System was initially installed in February, 1988 and modified in May, 1993 to accommodate the addition of a pump and a split of cooling paths. This paper will also discuss the PLC's reliability and operational history.
{"title":"Operation of a Fluorinert cooling system for the TFTR TF coils and TFTR Coil Flowswitch Monitoring System modification to accommodate the TF Alternate Cooling System (Fluorinert)","authors":"G. Barnes, G. R. Walton, D. Bashore","doi":"10.1109/FUSION.1993.518342","DOIUrl":"https://doi.org/10.1109/FUSION.1993.518342","url":null,"abstract":"The Tokamak Fusion Test Reactor (TFTR) at the Princeton Plasma Physics Laboratory (PPPL) employs Toroidal Field (TF) and Poloidal Field (PF) coils to generate the magnetic fields required for fusion plasma confinement. Several small deionized cooling water leaks in several TF coils had occurred and impacted TFTR operations. In order to prepare the TF coils for D-T experimental runs, the TF coil's deionized water coolant was replaced with a dielectric fluid-perfluoroheptane (3M Fluorinert PF-5070) in May 1993. The TF Alternate Cooling System (Fluorinert) is now in the operational phase. This paper describes how the TF Alternate Cooling System (Fluorinert) is operationally different from its predecessor (water) and how the Water Systems Group participated in the testing of the system. Operations and the special techniques that the TF Alternate Cooling System requires for maintenance are a part of this paper. The training of the Water Systems personnel in order to effectively monitor the controls and equipment for Fluorinert cooling during tritium operations is also addressed. This paper also describes the application of commercially available hardware and software to mitigate the consequences of a coil cooling flow loss. The TFTR Coil Flowswitch Monitoring System is devoted to coil protection and employs a programmable logic controller (PLC) to monitor the cooling flow at the outlet of each coil's cooling path. The system inhibits field coil rectifier operation when failure conditions exist and employs various redundant and stuck mode features. The Coil Flowswitch Monitoring System was initially installed in February, 1988 and modified in May, 1993 to accommodate the addition of a pump and a split of cooling paths. This paper will also discuss the PLC's reliability and operational history.","PeriodicalId":365814,"journal":{"name":"15th IEEE/NPSS Symposium. Fusion Engineering","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"1993-10-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"122787180","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.1993.518375
T. Inoue, K. Miyamoto, M. Mizuno, Y. Okumura, Y. Ohara, G. Ackerman, C. F. Chan, W. Cooper, J. Kwan, M. Vella
A test of intense beam production with a JAERI negative ion source and an ESQ accelerator is in progress under US-JAPAN collaborative program between JAERI and LBL. In the first series of the experiments, a merging beam system with an extractor composed of spherical shaped curved grids are used to merge multiple-beams into a single high current beam to be accelerated by an ESQ accelerator. The H/sup -/ ions of 104 mA were extracted from nineteen apertures (10 mm dia.) drilled in an area of 80 mm/spl phi/. Using the merging beam system with a focal length of 150 mm, the beamlets were successfully focused and the beam envelope diameter was compressed to 23 mm. Focusing angle of the merging beam envelope at the entrance of the accelerator could be reduced within the range of -30 (converging)/spl sim/+30 (diverging) mrad, which is acceptable in the ESQ accelerator to obtain a high energy beam.
{"title":"Merging beam experiment of intense negative ions for advanced compact neutral beam injectors","authors":"T. Inoue, K. Miyamoto, M. Mizuno, Y. Okumura, Y. Ohara, G. Ackerman, C. F. Chan, W. Cooper, J. Kwan, M. Vella","doi":"10.1109/FUSION.1993.518375","DOIUrl":"https://doi.org/10.1109/FUSION.1993.518375","url":null,"abstract":"A test of intense beam production with a JAERI negative ion source and an ESQ accelerator is in progress under US-JAPAN collaborative program between JAERI and LBL. In the first series of the experiments, a merging beam system with an extractor composed of spherical shaped curved grids are used to merge multiple-beams into a single high current beam to be accelerated by an ESQ accelerator. The H/sup -/ ions of 104 mA were extracted from nineteen apertures (10 mm dia.) drilled in an area of 80 mm/spl phi/. Using the merging beam system with a focal length of 150 mm, the beamlets were successfully focused and the beam envelope diameter was compressed to 23 mm. Focusing angle of the merging beam envelope at the entrance of the accelerator could be reduced within the range of -30 (converging)/spl sim/+30 (diverging) mrad, which is acceptable in the ESQ accelerator to obtain a high energy beam.","PeriodicalId":365814,"journal":{"name":"15th IEEE/NPSS Symposium. Fusion Engineering","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"1993-10-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"122010275","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.1993.518360
H. Becker, R. Myatt
The ALCATOR C-MOD tokamak employs poloidal field (PF) coils inside the toroidal field (TF) coils. C10100 copper coaxial current leads pass radially through an 18 tesla toroidal field to reach the terminals of the ohmic heating (OH) coil. In addition, there are radial and poloidal fields on the order of 2 Tesla near the OH terminals. The 50 kA lead currents interact with those fields to produce 900 kN/m forces which act in opposite directions on the coaxial conductors. The net load is zero on the conductor pair. However, the internal forces and moments cause stresses in the outer conductor tube that depend strongly on the size of the air gap between the tube and the insulation. Analysis indicates a peak stress of 430 MPa for a 0.19 mm air gap. The stress field is complicated by a 90 degree bend to vertical at the terminal block. Internal loads in the bend region lead to bourdon tube behavior, which produces longitudinal bending stresses in the coax. The coax must resist fatigue failure for reversed 50,000 pulses with a Safety Factor of 10. Ironically, this component is considered innocuous, and rarely given such attention, simply because there is no net load on a coax in a transverse field.
{"title":"Structural behavior of coaxes in transverse magnetic fields","authors":"H. Becker, R. Myatt","doi":"10.1109/FUSION.1993.518360","DOIUrl":"https://doi.org/10.1109/FUSION.1993.518360","url":null,"abstract":"The ALCATOR C-MOD tokamak employs poloidal field (PF) coils inside the toroidal field (TF) coils. C10100 copper coaxial current leads pass radially through an 18 tesla toroidal field to reach the terminals of the ohmic heating (OH) coil. In addition, there are radial and poloidal fields on the order of 2 Tesla near the OH terminals. The 50 kA lead currents interact with those fields to produce 900 kN/m forces which act in opposite directions on the coaxial conductors. The net load is zero on the conductor pair. However, the internal forces and moments cause stresses in the outer conductor tube that depend strongly on the size of the air gap between the tube and the insulation. Analysis indicates a peak stress of 430 MPa for a 0.19 mm air gap. The stress field is complicated by a 90 degree bend to vertical at the terminal block. Internal loads in the bend region lead to bourdon tube behavior, which produces longitudinal bending stresses in the coax. The coax must resist fatigue failure for reversed 50,000 pulses with a Safety Factor of 10. Ironically, this component is considered innocuous, and rarely given such attention, simply because there is no net load on a coax in a transverse field.","PeriodicalId":365814,"journal":{"name":"15th IEEE/NPSS Symposium. Fusion Engineering","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"1993-10-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"122013510","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.1993.518345
D. Gao, J.M. Li, S.R. Wang, X. Liu, W.H. Zhu, Y. Xue, J.F. Wu, X.F. Xu
The HT-7 Superconducting Tokamak is being built in Hefei, China. It is a device reconstructed and upgraded from T-7 Tokamak of Russia. This project is a co-operating item of fusion research between Russia and China. The Research and Manufacturing Center (RMC), ASIPP is responsible for the fabrication and assembly of HT-7. The design of HT-7 was carried out by both of Russian and Chinese engineers in 1991, and the main parts of the machine were fabricated in 1992. The preassembly of HT-7 was completed in April, 1993. This paper emphasizes on the manufacturing steps necessary to produce the HT-7 and a series of technological methods to overcome the key techniques.
{"title":"The fabrication and preassembly of HT-7 Superconducting Tokamak","authors":"D. Gao, J.M. Li, S.R. Wang, X. Liu, W.H. Zhu, Y. Xue, J.F. Wu, X.F. Xu","doi":"10.1109/FUSION.1993.518345","DOIUrl":"https://doi.org/10.1109/FUSION.1993.518345","url":null,"abstract":"The HT-7 Superconducting Tokamak is being built in Hefei, China. It is a device reconstructed and upgraded from T-7 Tokamak of Russia. This project is a co-operating item of fusion research between Russia and China. The Research and Manufacturing Center (RMC), ASIPP is responsible for the fabrication and assembly of HT-7. The design of HT-7 was carried out by both of Russian and Chinese engineers in 1991, and the main parts of the machine were fabricated in 1992. The preassembly of HT-7 was completed in April, 1993. This paper emphasizes on the manufacturing steps necessary to produce the HT-7 and a series of technological methods to overcome the key techniques.","PeriodicalId":365814,"journal":{"name":"15th IEEE/NPSS Symposium. Fusion Engineering","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"1993-10-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"116750593","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.1993.518285
J. R. Robins, K. Woodall, G. Woo, D. Bellamy, S. Sood, C. Fong, D.T. Lee, M. Tanaka, K. Kalyanam, M. Hare, A. Busigin, F. Adamek, O. Kveton
The Tritium Purification System (TPS) for the TFTR at Princeton has been designed and built by Ontario Hydro/CFFTP on a fast-track schedule of about 15 months. This paper describes the design of the system, the technical challenges, and the innovative solutions required to meet the schedule, space and inventory constraints.
{"title":"Tritium Purification System for TFTR","authors":"J. R. Robins, K. Woodall, G. Woo, D. Bellamy, S. Sood, C. Fong, D.T. Lee, M. Tanaka, K. Kalyanam, M. Hare, A. Busigin, F. Adamek, O. Kveton","doi":"10.1109/FUSION.1993.518285","DOIUrl":"https://doi.org/10.1109/FUSION.1993.518285","url":null,"abstract":"The Tritium Purification System (TPS) for the TFTR at Princeton has been designed and built by Ontario Hydro/CFFTP on a fast-track schedule of about 15 months. This paper describes the design of the system, the technical challenges, and the innovative solutions required to meet the schedule, space and inventory constraints.","PeriodicalId":365814,"journal":{"name":"15th IEEE/NPSS Symposium. Fusion Engineering","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"1993-10-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"128480778","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.1993.518278
John A Urbahn, Martin Greenwald, Ian H. Hutchinson, Allan F Henry
A twenty barrel hydrogen pellet has been designed, built and tested for use on the Alcator C-Mod Tokamak at MIT. The design is the first to use a closed cycle helium refrigerator to cool the thermal system components and employs in-situ condensation of the fuel gas. The design of the pellet tracker a diagnostic for following the trajectory of the pellets in time is outlined. This paper discusses the design goals and engineering features of the injector as well as laboratory performance results. Tracker data obtained during injection experiments is also presented.
{"title":"The design and performance of a twenty barrel hydrogen pellet injector for Alcator C-mod","authors":"John A Urbahn, Martin Greenwald, Ian H. Hutchinson, Allan F Henry","doi":"10.1109/FUSION.1993.518278","DOIUrl":"https://doi.org/10.1109/FUSION.1993.518278","url":null,"abstract":"A twenty barrel hydrogen pellet has been designed, built and tested for use on the Alcator C-Mod Tokamak at MIT. The design is the first to use a closed cycle helium refrigerator to cool the thermal system components and employs in-situ condensation of the fuel gas. The design of the pellet tracker a diagnostic for following the trajectory of the pellets in time is outlined. This paper discusses the design goals and engineering features of the injector as well as laboratory performance results. Tracker data obtained during injection experiments is also presented.","PeriodicalId":365814,"journal":{"name":"15th IEEE/NPSS Symposium. Fusion Engineering","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"1993-10-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"123361001","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.1993.518302
M. Thompson, T. Carroll, T. Gibney, J. Snyder
Reflecting the increasingly national character of magnetic fusion experiments, the Tokamak Fusion Test Reactor (TFTR) at Princeton Plasma Physics Laboratory (PPPL) now supports off-site real-time collaboration in the experimental program. Two types of remote access are supported. Observers can obtain up-to-date information on the purpose and progress of the day's experiment and instantaneous display of analyzed data after each machine pulse. In addition,, collaborators can exercise control over specific diagnostic apparatus. This paper discusses how various aspects of the system work and some of the problems that were encountered in developing the system.
{"title":"Real-time remote access to TFTR experimental data","authors":"M. Thompson, T. Carroll, T. Gibney, J. Snyder","doi":"10.1109/FUSION.1993.518302","DOIUrl":"https://doi.org/10.1109/FUSION.1993.518302","url":null,"abstract":"Reflecting the increasingly national character of magnetic fusion experiments, the Tokamak Fusion Test Reactor (TFTR) at Princeton Plasma Physics Laboratory (PPPL) now supports off-site real-time collaboration in the experimental program. Two types of remote access are supported. Observers can obtain up-to-date information on the purpose and progress of the day's experiment and instantaneous display of analyzed data after each machine pulse. In addition,, collaborators can exercise control over specific diagnostic apparatus. This paper discusses how various aspects of the system work and some of the problems that were encountered in developing the system.","PeriodicalId":365814,"journal":{"name":"15th IEEE/NPSS Symposium. Fusion Engineering","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"1993-10-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"121351273","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.1993.518354
Z. Peng, Liu Guangwu, Luo Cuiwen, L. Chunsheng, Fang Shuiqian, L. Qiang, Yu Chaowei, Li Jieping, Y. Ping
The SWIP-RFP device has a thin stainless steel liner and its vacuum chamber is surrounded by a thick aluminum alloy shell. The toroidal coil series is a connection of 32 one-turn coils with an insulation among the coils of 5 kV. The air-core transformer has 32 turns and the poloidal field coil system is of 8 two-turn type. The insulation among the poloidal coils for the full operation voltage is 20 kV.
{"title":"Reversed field pinch experiments on SWIP-RFP device","authors":"Z. Peng, Liu Guangwu, Luo Cuiwen, L. Chunsheng, Fang Shuiqian, L. Qiang, Yu Chaowei, Li Jieping, Y. Ping","doi":"10.1109/FUSION.1993.518354","DOIUrl":"https://doi.org/10.1109/FUSION.1993.518354","url":null,"abstract":"The SWIP-RFP device has a thin stainless steel liner and its vacuum chamber is surrounded by a thick aluminum alloy shell. The toroidal coil series is a connection of 32 one-turn coils with an insulation among the coils of 5 kV. The air-core transformer has 32 turns and the poloidal field coil system is of 8 two-turn type. The insulation among the poloidal coils for the full operation voltage is 20 kV.","PeriodicalId":365814,"journal":{"name":"15th IEEE/NPSS Symposium. Fusion Engineering","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"1993-10-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"124068918","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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