15th IEEE/NPSS Symposium. Fusion Engineering最新文献_第7页

Status and test results of the Tokamak-15 superconducting toroidal field coil 托卡马克-15超导环形场线圈的现状和测试结果

15th IEEE/NPSS Symposium. Fusion Engineering Pub Date : 1993-10-11 DOI: 10.1109/FUSION.1993.518527

I. Anashkin, V.V. Asmalovksy, A. N. Vertiporokh, D. Ivanov, I. A. Posadsky, P. Khvostenko

引用次数: 2

Proposed high speed pellet injection system "HIPEL" for Large Helical Device 提出了用于大型螺旋装置的高速颗粒注射系统“HIPEL”

15th IEEE/NPSS Symposium. Fusion Engineering Pub Date : 1993-10-11 DOI: 10.1109/FUSION.1993.518276

S. Sudo, M. Kanno, H. Kaneko, S. Saka, T. Shirai, T. Baba

引用次数: 1

IDEAL preconceptual design development 理想的概念前设计开发

15th IEEE/NPSS Symposium. Fusion Engineering Pub Date : 1993-10-11 DOI: 10.1109/FUSION.1993.518350

R. Gentzlinger, S. Mendelsohn, B. Abel, I. Birnbaum, U. Christensen, S. Kalsi, J. Mueller, M. Phillips, J. Swinton, D. Weissenburger, S. Cohen, E. Fredd, R. Majeski, R. Motley, R. Walls

引用次数: 0

Tools and frameworks supporting TPX and ITER design collaborations 支持TPX和ITER设计协作的工具和框架

15th IEEE/NPSS Symposium. Fusion Engineering Pub Date : 1993-10-11 DOI: 10.1109/FUSION.1993.518300

W. Stark, V.J. Abraitis, S. Davis, R. Simmons, S.M. Young, C. Flanagan

引用次数: 0

Limitations of power conversion systems under transient loads and impact on the pulsed tokamak power reactor 瞬态负荷下功率转换系统的局限性及其对脉冲托卡马克功率堆的影响

15th IEEE/NPSS Symposium. Fusion Engineering Pub Date : 1993-10-11 DOI: 10.1109/FUSION.1993.518474

G. Sager, C. Wong, D.D. Kapich, C. Mcdonald, R. Schleicher

引用次数: 3

Two-gigawatt burst-mode operation of the intense microwave prototype (IMP) free-electron laser (FEL) for the microwave tokamak experiment (MTX) 用于微波托卡马克实验(MTX)的强微波原型(IMP)自由电子激光器(FEL)的2千兆瓦爆发模式操作

15th IEEE/NPSS Symposium. Fusion Engineering Pub Date : 1993-10-11 DOI: 10.1109/FUSION.1993.518543

B. Felker, S. Allen, H. Bell, J. Bowman, M. Delong, M. Fenstermacher, S. W. Ferguson, W. F. Fields, D. Hathaway, E. Hooper, S. Hulsey, M. Jackson, D. Lang, C. Lasnier, M. Makowski, J. Moller, W. Meyer, D. Nilson, D. Peterson, D. Seilhymer, B. Stallard

{"title":"Two-gigawatt burst-mode operation of the intense microwave prototype (IMP) free-electron laser (FEL) for the microwave tokamak experiment (MTX)","authors":"B. Felker, S. Allen, H. Bell, J. Bowman, M. Delong, M. Fenstermacher, S. W. Ferguson, W. F. Fields, D. Hathaway, E. Hooper, S. Hulsey, M. Jackson, D. Lang, C. Lasnier, M. Makowski, J. Moller, W. Meyer, D. Nilson, D. Peterson, D. Seilhymer, B. Stallard","doi":"10.1109/FUSION.1993.518543","DOIUrl":"https://doi.org/10.1109/FUSION.1993.518543","url":null,"abstract":"The MTX explored the plasma heating effects of 140 GHz microwaves from both Gyrotrons and from the IMP FEL wiggler. The Gyrotron was long pulse length (0.5 seconds maximum) and the FEL produced short-pulse length, high-peak power, single and burst modes of 140 GHz microwaves. Full-power operations of the IMP FEL wiggler were commenced in April of 1992 and continued into October of 1992. The Experimental Test Accelerator II (ETA-II) provided a 50-nanosecond, 6-MeV, 2-3 kAmp electron beam that was introduced co-linear into the IMP FEL with a 140 GHz Gyrotron master oscillator (MO). The FEL was able to amplify the MO signal from approximately 7 kW to peaks consistently in the range of 1-2 GW. This microwave pulse was transmitted into the MTX and allowed the exploration of the linear and non-linear effects of short pulse, intense power in the MTX plasma. Single pulses were used to explore and gain operating experience in the parameter space of the IMP FEL, and finally evaluate transmission and absorption in the MTX. Single-pulse operations were repeatable. After the MTX was shut down burst-mode operations were successful at 2 kHz. This paper will describe the IMP FEL, Microwave Transmission System to MTX, the diagnostics used for measurements, and tile operations of the entire Microwave system. A discussion of correlated and uncorrelated errors that affect FEL performance will be made. Linear and nonlinear absorption data of the microwaves in the MTX plasma will be presented.","PeriodicalId":365814,"journal":{"name":"15th IEEE/NPSS Symposium. Fusion Engineering","volume":"21 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":"127174234","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: 0

Heat transfer in MHD laminar flow through a rectangular channel in the plasma facing components of fusion reactors MHD层流在核聚变反应堆等离子体面组件矩形通道中的传热

15th IEEE/NPSS Symposium. Fusion Engineering Pub Date : 1993-10-11 DOI: 10.1109/FUSION.1993.518539

K. Takase, M. Z. Hasan

{"title":"Heat transfer in MHD laminar flow through a rectangular channel in the plasma facing components of fusion reactors","authors":"K. Takase, M. Z. Hasan","doi":"10.1109/FUSION.1993.518539","DOIUrl":"https://doi.org/10.1109/FUSION.1993.518539","url":null,"abstract":"Convective heat transfer in MHD laminar flow through a square duct in the plasma facing components (PFCs) of fusion reactors is analyzed numerically to investigate the effects of a transverse magnetic field and the nonuniformity of surface heat flux. As in the case of non-MHD laminar flow, analyzed earlier, the corners of the plasma facing (PF) side are possible hot-spot areas; the presence of a transverse magnetic field does not alleviate this situation to any significant degree. The nonuniformity of surface heat flux nearly cancels this increase of Nu at the PF side. At Hartmann number (Ha) of 40, Nu at the center increases from 6.9 to 23, but at the corner from 2.2 to 3.2 only with uniform heat flux. But, as the extent of nonuniformity of surface heat flux increases, Nu at the center decreases rapidly. This effect, however, saturates rapidly with the increase of the nonuniformity of heat flux. The increase of Nu with Ha is very small for large nonuniformity of the heat flux. Under this condition, Nu at the center of the plasma facing side, is 2.8 at Ha=O, 3.02 at Ha=16 and 3.4 at Ha=400. At the corner of the PF side, the corresponding values of Nu are 2.65, 2.88, and 3.0, respectively. The effect of Ha on entry length is small for highly nonuniform heat flux.","PeriodicalId":365814,"journal":{"name":"15th IEEE/NPSS Symposium. Fusion Engineering","volume":"2010 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":"127350854","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

Earth faults during RFX initial operations RFX初始运行时接地故障

15th IEEE/NPSS Symposium. Fusion Engineering Pub Date : 1993-10-11 DOI: 10.1109/FUSION.1993.518346

F. Bellina, G. Chitarin, M. Guarnieri, A. Stella, F. Trevisan

引用次数: 1

TPX poloidal limiter design TPX极向限幅器设计

15th IEEE/NPSS Symposium. Fusion Engineering Pub Date : 1993-10-11 DOI: 10.1109/FUSION.1993.518456

H.C. Mantz, D. Bowers, J. Haines, F. Williams

引用次数: 2

/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 /sup 3/He用于TEXTOR的高功率中性束与/sup 4/He、氘和氢的55 KeV粒子束和真空系统数据的比较

15th IEEE/NPSS Symposium. Fusion Engineering Pub Date : 1993-10-11 DOI: 10.1109/FUSION.1993.518377

R. Uhlemann, H. Reimer, M. Lochter

引用次数: 0