15th IEEE/NPSS Symposium. Fusion Engineering最新文献_第2页

Control of the vacuum vessel temperature in RFX RFX真空容器温度的控制

15th IEEE/NPSS Symposium. Fusion Engineering Pub Date : 1993-10-11 DOI: 10.1109/FUSION.1993.518319

P. Campostrini, M. Fauri, G. Marchiori, P. Sonato, S. Vitturi, G. Zollino

引用次数: 0

Use of OPEN systems for control, analysis and data acquisition of the DIII-D tokamak 使用OPEN系统对DIII-D托卡马克进行控制、分析和数据采集

15th IEEE/NPSS Symposium. Fusion Engineering Pub Date : 1993-10-11 DOI: 10.1109/FUSION.1993.518298

P.A. Henline

引用次数: 10

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) 为TFTR TF线圈和TFTR线圈流量开关监控系统改装以适应TF替代冷却系统(氟惰性)的氟化冷却系统的运行

15th IEEE/NPSS Symposium. Fusion Engineering Pub Date : 1993-10-11 DOI: 10.1109/FUSION.1993.518342

G. Barnes, G. R. Walton, D. Bashore

{"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":"176 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":"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}

引用次数: 6

Merging beam experiment of intense negative ions for advanced compact neutral beam injectors 先进紧凑型中性束注入器强负离子合并束实验

15th IEEE/NPSS Symposium. Fusion Engineering Pub Date : 1993-10-11 DOI: 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

引用次数: 1

Structural behavior of coaxes in transverse magnetic fields 横向磁场中同轴线圈的结构特性

15th IEEE/NPSS Symposium. Fusion Engineering Pub Date : 1993-10-11 DOI: 10.1109/FUSION.1993.518360

H. Becker, R. Myatt

{"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":"12 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":"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}

引用次数: 4

The fabrication and preassembly of HT-7 Superconducting Tokamak HT-7超导托卡马克的研制与预装

15th IEEE/NPSS Symposium. Fusion Engineering Pub Date : 1993-10-11 DOI: 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

引用次数: 1

Tritium Purification System for TFTR TFTR氚净化系统

15th IEEE/NPSS Symposium. Fusion Engineering Pub Date : 1993-10-11 DOI: 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

引用次数: 8

The design and performance of a twenty barrel hydrogen pellet injector for Alcator C-mod c型反应器用20管氢气颗粒喷射器的设计与性能

15th IEEE/NPSS Symposium. Fusion Engineering Pub Date : 1993-10-11 DOI: 10.1109/FUSION.1993.518278

John A Urbahn, Martin Greenwald, Ian H. Hutchinson, Allan F Henry

引用次数: 2

Real-time remote access to TFTR experimental data 实时远程访问TFTR实验数据

15th IEEE/NPSS Symposium. Fusion Engineering Pub Date : 1993-10-11 DOI: 10.1109/FUSION.1993.518302

M. Thompson, T. Carroll, T. Gibney, J. Snyder

引用次数: 2

Reversed field pinch experiments on SWIP-RFP device 在SWIP-RFP装置上的反向场夹紧实验

15th IEEE/NPSS Symposium. Fusion Engineering Pub Date : 1993-10-11 DOI: 10.1109/FUSION.1993.518354

Z. Peng, Liu Guangwu, Luo Cuiwen, L. Chunsheng, Fang Shuiqian, L. Qiang, Yu Chaowei, Li Jieping, Y. Ping

引用次数: 0