[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering最新文献

Design of a coil to correct magnetic field errors on the DIII-D tokamak 用于校正DIII-D托卡马克磁场误差的线圈设计

[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-11-01 DOI: 10.1109/FUSION.1991.218669

J. Scoville, R. L. La Haye

引用次数: 4

The design and fabrication of a toroidally continuous cryocondensation pump for the DIII-D advanced divertor DIII-D高级导流器环形连续冷凝泵的设计与制造

[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-11-01 DOI: 10.1109/FUSION.1991.218648

J.P. Smith, C. Baxi, E. Reis, M. Schaffer, K. Schaubel, M. Menon

{"title":"The design and fabrication of a toroidally continuous cryocondensation pump for the DIII-D advanced divertor","authors":"J.P. Smith, C. Baxi, E. Reis, M. Schaffer, K. Schaubel, M. Menon","doi":"10.1109/FUSION.1991.218648","DOIUrl":"https://doi.org/10.1109/FUSION.1991.218648","url":null,"abstract":"A cryocondensation pump will be installed in the baffle chamber of the DIII-D tokamak in the spring of 1992. The design is complete and fabrication of this pump is in progress. The purpose of the pump is to study plasma density control by pumping the divertor. The pump is toroidally continuous, approximately 10 m long, in the lower outer corner of the vacuum vessel interior. It consists of a 1-m/sup 2/ liquid-helium-cooled surface surrounded by a liquid-nitrogen-cooled shield to limit the heat load on the helium-cooled surface. The stainless steel liquid nitrogen shell has a copper coating on it to enhance thermal conductivity but the coating is broken to keep the toroidal electrical resistance high. The liquid-nitrogen-cooled surface is surrounded by a radiation/particle shield to prevent energetic particles from impacting and releasing condensed water molecules. The whole pump is supported off the water-cooled vacuum vessel wall. A testing program was used to develop coating techniques to enhance heat transfer and emissivity of the various surfaces. Fabrication tests were done to determine the best method of attaching the liquid nitrogen flow tubes to their shield surfaces. A prototype sector of the pump was built to verify fabrication and assembly techniques.<<ETX>>","PeriodicalId":318951,"journal":{"name":"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering","volume":"1 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1991-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"129054895","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: 5

The charge exchange recombination diagnostic system on the DIII-D tokamak DIII-D托卡马克上的电荷交换复合诊断系统

[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-11-01 DOI: 10.1109/FUSION.1991.218656

P. Gohil, K. Burrell, R. Groebner, J. Kim, W. Martin, E. McKee, R. Seraydarian

{"title":"The charge exchange recombination diagnostic system on the DIII-D tokamak","authors":"P. Gohil, K. Burrell, R. Groebner, J. Kim, W. Martin, E. McKee, R. Seraydarian","doi":"10.1109/FUSION.1991.218656","DOIUrl":"https://doi.org/10.1109/FUSION.1991.218656","url":null,"abstract":"The charge exchange recombination, (CER) diagnostic system on the DIII-D tokamak is used to make spatially and temporally resolved measurements of the ion temperature and toroidal and poloidal rotation velocities. This is performed through visible spectroscopic measurements of the Doppler-broadened and Doppler-shifted He II 468.6-nm, CVI 529.1-nm, and BV 494.5-nm spectral lines which have been excited by charge exchange recombination interactions between the fully stripped ions and the neutral atoms from the heating beams. The plasma viewing optics comprises 32 viewing chords spanning a typical plasma minor radius of 63 cm across the midplane, of which 15 spatial chords span 4.2 cm at the plasma edge just within the separatrix and provide a chord-to-chord spatial resolution of 0.3 cm. Fast camera readout electronics can provide a temporal resolution of 260 mu s per time slice, but the effective minimum integration time, at present, is 1 ms, which is limited by the detected photon flux from the plasma and the decay times of the phosphors used on the multichannel plate image intensifiers. Significant changes in the edge plasma radial electric field at the L-H transition have been observed, as determined from the CER measurements, and these results are being extensively compared to theories which consider the effects of sheared electric fields on plasma turbulence.<<ETX>>","PeriodicalId":318951,"journal":{"name":"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering","volume":"4 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1991-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"115857068","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: 16

Timing system for neutral beam injection on the DIII-D tokamak DIII-D托卡马克中性束注入定时系统

[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-11-01 DOI: 10.1109/FUSION.1991.218723

G. Bramson

引用次数: 0

Modeling and measurement of the motion of the DIII-D vacuum vessel during vertical instabilities DIII-D真空容器在垂直不稳定状态下的运动建模与测量

[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-11-01 DOI: 10.1109/FUSION.1991.218831

E. Reis, R. Blevins, T. Jensen, J. Luxon, P. Petersen, E. Strait

引用次数: 0

The DIII-D tokamak TROUBLE report database DIII-D托卡马克故障报告数据库

[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-11-01 DOI: 10.1109/FUSION.1991.218733

P. Petersen, S. Miller

引用次数: 5

An advanced plasma control system for the DIII-D tokamak DIII-D托卡马克的先进等离子体控制系统

[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-11-01 DOI: 10.1109/FUSION.1991.218736

J. Ferron, A. Kellman, E. McKee, T. Osborne, P. Petrach, T. Taylor, J. Wight, E. Lazarus

引用次数: 23

Displaying DIII-D plasma data using DEC's X Window System 使用DEC的X窗口系统显示DIII-D等离子体数据

[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-11-01 DOI: 10.1109/FUSION.1991.218734

K. L. Greene

引用次数: 0

Eight channel-16 bit, bidirectional analog to digital monitoring and control system 8通道-16位，双向模拟数字监控系统

[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-11-01 DOI: 10.1109/FUSION.1991.218715

J.C. Allen, R. Callis, W. Cary, T. E. Harris, A. Nerem

引用次数: 1

Particle control in the DIII-D advanced divertor DIII-D高级导流器中的颗粒控制

[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-11-01 DOI: 10.1109/FUSION.1991.218919

M. J. Schaffer, S. Lippmann, M. Mahdavi, T. Petrie, R. Stambaugh, J. Hogan, C. Klepper, P. Mioduszewski, L. W. Owen, D. N. Hill, M. Rensink, D. Buchenauer

引用次数: 1