2009 23rd IEEE/NPSS Symposium on Fusion Engineering最新文献_第5页

Fuelling and disruption mitigation in ITER ITER的加注和干扰缓解

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226494

S. Maruyama, Y. Yang, M. Sugihara, R. Pitts, B. Li, W. Li, L. Baylor, S. Combs, S. Meitner

引用次数: 16

Simulation results for new NSTX HHFW antenna straps design by using microwave studio 利用微波工作室设计新型NSTX HHFW天线带的仿真结果

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226421

C. Kung, R. Ellis, C. Brunkhorst, N. Greenough, E. Fredd, A. Castano, D. Miller, G. D'Amico, R. Yager, J. Hosea, J. Wilson, P. Ryan

引用次数: 0

Operation and characterization of a Water Detritiation Facility at the Tritium Laboratory Karlsruhe 卡尔斯鲁厄氚实验室水脱水设备的运行和特性

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226511

R. Michling, I. Cristescu, F. Eichelhardt, S. Welte, W. Wurster

引用次数: 3

Robust control of the poloidal magnetic flux profile in the presence of unmodeled dynamics 存在未建模动力学的极向磁通分布的鲁棒控制

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226466

Y. Ou, Chao Xu, E. Schuster

{"title":"Robust control of the poloidal magnetic flux profile in the presence of unmodeled dynamics","authors":"Y. Ou, Chao Xu, E. Schuster","doi":"10.1109/FUSION.2009.5226466","DOIUrl":"https://doi.org/10.1109/FUSION.2009.5226466","url":null,"abstract":"The potential operation of a tokamak fusion reactor in a highly-efficient, steady-state mode is directly related to the achievement of certain types of radial profiles for the current flowing toroidally in the device. The evolution in time of the toroidal current profile in tokamaks is related to the evolution of the poloidal magnetic flux profile, which is modeled in normalized cylindrical coordinates using a nonlinear partial differential equation (PDE) usually referred to as the magnetic diffusion equation. We propose a robust control scheme to regulate the poloidal magnetic flux profile in tokamaks in the presence of model uncertainties. These uncertainties come mainly from the resistivity term of the magnetic diffusion equation. First we either simulate the magnetic diffusion equation or carry out experiments to generate data ensembles, from which we then extract the most energetic modes to obtain a reduced order model based on proper orthogonal decomposition (POD) and Galerkin projection. The obtained reduced-order model corresponds to a linear state space representation with uncertainty. Taking advantage of the structure of the state matrices, the reduced order model is reformulated into a robust control framework, with the resistivity term as an uncertain parameter. An H∞ controller is designed to minimize the regulation/tracking error. Finally, the synthesized model-based robust controller is tested in simulations.","PeriodicalId":236460,"journal":{"name":"2009 23rd IEEE/NPSS Symposium on Fusion Engineering","volume":"158 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2009-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"122269386","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

Progress in design integration and configuration control of the ITER machine baseline ITER机器基线设计集成与组态控制研究进展

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226475

I. Kuehn, J. Cordier, S. Chiocchio, B. Levesy, B. Manfreo, J. Reich, G. Rigoni

引用次数: 2

Mobile tiles for inertial fusion first wall/blanket 移动瓷砖用于惯性聚变第一墙/毯

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226442

M. Sawan, E. Marriott, C. S. Aplin, L. Snead

引用次数: 1

An overview of the iter in-vessel coil systems iter容器内盘管系统概述

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226519

P. Heitzenroeder, A. Brooks, J. Chrzanowski, F. Dahlgren, R. Hawryluk, G. Loesser, C. Neumeyer, C. Mansfield, J. Cordier, D. Campbell, G. Johnson, A. Martin, P. Rebut, J. Tao, J.P. Smith, M. Schaffer, D. Humphreys, P. Fogarty, B. Nelson, R. Reed

引用次数: 25

High power, high voltage FETs in linear applications: A user's perspective 线性应用中的高功率、高电压场效应管:用户视角

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/fusion.2009.5226417

N. Greenough, E. Fredd, S. Depasquale

引用次数: 0

Numerical analysis of using a fluidized bed as a prototypic mass production device for IFE target layering 流化床作为IFE靶层原型量产装置的数值分析

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226372

K. Boehm, A. Raffray, N. Alexander, D. Frey, D. Goodin

{"title":"Numerical analysis of using a fluidized bed as a prototypic mass production device for IFE target layering","authors":"K. Boehm, A. Raffray, N. Alexander, D. Frey, D. Goodin","doi":"10.1109/FUSION.2009.5226372","DOIUrl":"https://doi.org/10.1109/FUSION.2009.5226372","url":null,"abstract":"A fluidized bed has been identified as a very promising method for mass production of Inertial Fusion Energy (IFE) targets. While large beds could be filled with many targets to provide large-scale production, a proof of principle can be achieved by small scale laboratory experiments. The nearisothermal environment required for smooth layering to meet the specifications for the ice layer can be maintained, in principle, around each target through the random movement and spin of individual targets in a precisely controlled gas stream. Pre-experimental numerical studies have been performed to define the window of parameters, in which the layering process can be expected to work optimally. These numerical analyses address several topics, including the effect of unbalanced spheres on the bed behavior and ultimately on the target thermal environment, as well as effects of target collisions. The influence of the thermal environment around an individual target on the layer formation needs to be assessed and used as input for the fluidized bed model, as it affects the unbalance of the individual spheres.","PeriodicalId":236460,"journal":{"name":"2009 23rd IEEE/NPSS Symposium on Fusion Engineering","volume":"27 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2009-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"131954898","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

Progress on the design and manufacturing of the mirrors for the ITER electron cyclotron heating and current drive upper launcher ITER电子回旋加速器加热和电流驱动上部发射装置反射镜的设计与制造进展

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226491

F. Sanchez, R. Bertizzolo, R. Chavan, A. Collazos, M. Henderson, J. Landis

引用次数: 3