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2009 23rd IEEE/NPSS Symposium on Fusion Engineering最新文献

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Advantages of high tolerance measurements in fusion environments applying photogrammetry 应用摄影测量技术在融合环境中进行高公差测量的优势
2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-08-28 DOI: 10.1109/FUSION.2009.5226446
T. Dodson, R. Ellis, C. Priniski, S. Raftopoulos, D. Stevens, M. Viola
{"title":"Advantages of high tolerance measurements in fusion environments applying photogrammetry","authors":"T. Dodson, R. Ellis, C. Priniski, S. Raftopoulos, D. Stevens, M. Viola","doi":"10.1109/FUSION.2009.5226446","DOIUrl":"https://doi.org/10.1109/FUSION.2009.5226446","url":null,"abstract":"Photogrammetry, a state-of-the-art technique of metrology employing digital photographs as the vehicle for measurement, has been investigated in the fusion environment. Benefits of this high tolerance methodology include relatively easy deployment for multiple point measurements and deformation/distortion studies. Depending on the equipment used, photogrammetric systems can reach tolerances of 25 microns (0.001 in) to 100 microns (0.004 in) on a 3-meter object. During the fabrication and assembly of the National Compact Stellarator Experiment (NCSX) the primary measurement systems deployed were CAD coordinate-based computer metrology equipment and supporting algorithms such as both interferometer-aided (IFM) and absolute distance measurementbased (ADM) laser trackers, as well as portable Coordinate Measurement Machine (CMM) arms. Photogrammetry was employed at NCSX as a quick and easy tool to monitor coil distortions incurred during welding operations of the machine assembly process and as a way to reduce assembly downtime for metrology processes. This paper will explore the use of photogrammetry on NCSX during field period assembly (FPA) and the results it achieved. It will also explore other applications of this method and discuss future plans for use.","PeriodicalId":236460,"journal":{"name":"2009 23rd IEEE/NPSS Symposium on Fusion Engineering","volume":"48 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2009-08-28","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"128877827","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
Application of high-performance aerogel insulating materials (analysis & test results) 高性能气凝胶绝缘材料的应用(分析及试验结果)
2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226454
P. Goranson, K. Freudenberg, G. McGinnis, L. Dudek, M. Zarnstorff
{"title":"Application of high-performance aerogel insulating materials (analysis & test results)","authors":"P. Goranson, K. Freudenberg, G. McGinnis, L. Dudek, M. Zarnstorff","doi":"10.1109/FUSION.2009.5226454","DOIUrl":"https://doi.org/10.1109/FUSION.2009.5226454","url":null,"abstract":"The NCSX stellarator core design is built around a 3-period, highly shaped plasma with an assembly of four magnet systems, the TF coils (TF), the Modular Coils (MC), the PF Coils (PF), and the Trim Coils, that surrounds an all welded Vacuum Vessel (VV). The VV features approximately 100 ports for heating, pumping, diagnostics, and maintenance access. The entire system is surrounded by a cryostat to permit operation of the coils at liquid nitrogen temperature. The VV and coils are assembled in 120° segments. The VV segments must be placed inside the MC by sliding the coils over each end of the vessel subassembly. Installation of the port extensions is done after this operation. They are slipped through access holes in the MC onto port stubs and welded on from inside. Figures 1 & 2 illustrate the assembly of the MC over a VV section and installation of TF and port extensions to complete a sector of the VV.","PeriodicalId":236460,"journal":{"name":"2009 23rd IEEE/NPSS Symposium on Fusion Engineering","volume":"35 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":"123432979","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: 2
Toroidal field coil thermal analysis for fast tokamak 快速托卡马克环形场线圈热分析
2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226393
V. Cocilovo, G. Calabrò, A. Cucchiaro, A. Pizzuto, G. Ramogida, C. Rita
{"title":"Toroidal field coil thermal analysis for fast tokamak","authors":"V. Cocilovo, G. Calabrò, A. Cucchiaro, A. Pizzuto, G. Ramogida, C. Rita","doi":"10.1109/FUSION.2009.5226393","DOIUrl":"https://doi.org/10.1109/FUSION.2009.5226393","url":null,"abstract":"A new facility for fusion, the Fusion Advanced Studies Torus (FAST), has been proposed to prepare ITER scenarios and to investigate non linear dynamics of energetic particles, relevant for the understanding of burning plasmas behavior, using fast ions accelerated by heating and current drive systems [1]. This new facility is considered an important tool also for the successful development of the demonstration/prototype reactor (DEMO), because the DEMO scenarios can take valuable advantage by a preparatory activity on devices smaller than ITER with sufficient flexibility and capable plasma conditions, before to testing them on ITER itself.","PeriodicalId":236460,"journal":{"name":"2009 23rd IEEE/NPSS Symposium on Fusion Engineering","volume":"257 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":"126749857","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: 1
Stabilization of the KSTAR power system for the first plasma operation 首次等离子体运行时KSTAR电力系统的稳定
2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226394
J. Kong, S. L. Hong, I. Hwang, J. Choi, C. Kim, D. Lee, Y. Kim, M. Kwon, B. Park, H. Yoo
{"title":"Stabilization of the KSTAR power system for the first plasma operation","authors":"J. Kong, S. L. Hong, I. Hwang, J. Choi, C. Kim, D. Lee, Y. Kim, M. Kwon, B. Park, H. Yoo","doi":"10.1109/FUSION.2009.5226394","DOIUrl":"https://doi.org/10.1109/FUSION.2009.5226394","url":null,"abstract":"The KSTAR(Korea Superconducting Tokamak Advanced Research) facility is composed of thirty superconducting magnets for plasma experiment. The electric power system for the first plasma operation is made up of various electric devices including 170 kV GIS, 154 kV 50 MVA transformer, 22.9 kV circuit breaker systems and RPC & HF systems. When PF MPS was operated, reactive power and harmonic currents of 1±12ns occurred instantaneously in the KSTAR electric power system due to the characteristics of the KSTAR superconducting coil for the first plasma generation. However, the measured voltage drop and harmonics seriously affect other experiment equipments as well. Therefore, the RPC & HF system for the superconducting tokamak device is important to compensate the reactive power and remove harmonics. In this paper, we discuss the stability of the electric power system and the operation results of the RPC & HF systems during the KSTAR first plasma operation. Also, the upgrade plan of the electric power system based on the KSTAR operation plan will be discussed.","PeriodicalId":236460,"journal":{"name":"2009 23rd IEEE/NPSS Symposium on Fusion Engineering","volume":"9 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":"122724605","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
Progress on the ITER electron cyclotron heating and current drive upper launcher steering mirror control system ITER电子回旋加速器加热及电流驱动上发射装置转向镜控制系统的研究进展
2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226520
A. Collazos, R. Bertizzolo, R. Chavan, F. Dolizy, F. Felici, T. Goodman, J. Landis, F. Sanchez, M. Henderson
{"title":"Progress on the ITER electron cyclotron heating and current drive upper launcher steering mirror control system","authors":"A. Collazos, R. Bertizzolo, R. Chavan, F. Dolizy, F. Felici, T. Goodman, J. Landis, F. Sanchez, M. Henderson","doi":"10.1109/FUSION.2009.5226520","DOIUrl":"https://doi.org/10.1109/FUSION.2009.5226520","url":null,"abstract":"The ITER ECRH upper launcher (UL) uses a steering mechanism assembly (SMA) to steer the beams in the appropriate location for controlling magnetohydrodynamic (MHD) activity in the plasma (NTMs and sawtooth oscillations).","PeriodicalId":236460,"journal":{"name":"2009 23rd IEEE/NPSS Symposium on Fusion Engineering","volume":"213 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":"122811928","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: 1
Transient thermal and stress response of a helium-cooled tungsten plate-type divertor 氦冷钨板型导流器的瞬态热应力响应
2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226430
X. Wang, A. Raffray, S. Malang
{"title":"Transient thermal and stress response of a helium-cooled tungsten plate-type divertor","authors":"X. Wang, A. Raffray, S. Malang","doi":"10.1109/FUSION.2009.5226430","DOIUrl":"https://doi.org/10.1109/FUSION.2009.5226430","url":null,"abstract":"A number of different helium-cooled divertor design concepts have been proposed for MFE fusion power plant application. The larger-scale helium-cooled Tungsten-alloy plate-type divertor configuration (typically 20 cm (tor.) × 100 cm (pol.) × 6 cm (rad.)) provides an advantage of reduction in number of assembly units in a power plant and the associated reduction in complexity and possibly costs. Transient thermal and thermomechanical responses of the divertor plate during the plant startup and shutdown operations have been analyzed with a coupled transient thermo-fluid and thermal-stress approach. Results are presented in this paper.","PeriodicalId":236460,"journal":{"name":"2009 23rd IEEE/NPSS Symposium on Fusion Engineering","volume":"45 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":"114465145","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
Integration of laser techniques in a remote handled compact system for tokamak in vessel tritium and dust inventory, control and removal 集成激光技术的远程处理紧凑型系统的托卡马克在容器氚和粉尘的库存，控制和去除
2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226378
C. Hernandez, H. Roche, C. Pocheau, M. Naiim-Habib, J. Patterlini, R. Sibois, M. Lapeyre, A. Semerok, L. Doceul, C. Grisolia
{"title":"Integration of laser techniques in a remote handled compact system for tokamak in vessel tritium and dust inventory, control and removal","authors":"C. Hernandez, H. Roche, C. Pocheau, M. Naiim-Habib, J. Patterlini, R. Sibois, M. Lapeyre, A. Semerok, L. Doceul, C. Grisolia","doi":"10.1109/FUSION.2009.5226378","DOIUrl":"https://doi.org/10.1109/FUSION.2009.5226378","url":null,"abstract":"During Tokamak operation, plasma interacts with the Plasma Facing Components (PFCs). Therefore, exposed matter is eroded and re-deposited on the surface by forming instable layers. For safety and operational reasons and due to the fact that these layers are able to trap part of the hydrogenated species (particularly tritium) in vessel inventory or pollute diagnostics, flake and produce dusts, these layers have to be, characterized and removed.","PeriodicalId":236460,"journal":{"name":"2009 23rd IEEE/NPSS Symposium on Fusion Engineering","volume":"637 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":"121988323","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
A decade of NSTX operations using collaborative software 使用协作软件的十年NSTX操作经验
2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226473
P. Sichta, W. Davis, J. Dong, D. Mastrovito, G. Tchilinguirian, Gretchen Zimmer
{"title":"A decade of NSTX operations using collaborative software","authors":"P. Sichta, W. Davis, J. Dong, D. Mastrovito, G. Tchilinguirian, Gretchen Zimmer","doi":"10.1109/FUSION.2009.5226473","DOIUrl":"https://doi.org/10.1109/FUSION.2009.5226473","url":null,"abstract":"Since the beginning of the National Spherical Torus Experiment's (NSTX) research activities in 1999, open-source and collaborative software have been used extensively for experimental operations. The software included Experimental Physics and Industrial Control System (EPICS) and the Model Data System plus (MDSplus). This paper will begin with a retrospective of ten years of integrated computing, control, and data analysis on NSTX. A variety of practical issues will be reviewed such as: system reliability, availability, and maintainability; using open source software with commercial-off-the-shelf (COTS) hardware; obsolescence and remaining current. Recent improvements, current status, and emerging issues will be presented. Numerous proposals for NSTX upgrades have been made that will extend the performance and operating lifetime of NSTX. In light of this, a collective strategy for improving NSTX's collaborative software model for a new decade of operations will be examined.","PeriodicalId":236460,"journal":{"name":"2009 23rd IEEE/NPSS Symposium on Fusion Engineering","volume":"12 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":"124564127","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: 2
Analysis of DIII-D neutral beam power systems for 10 second operation DIII-D中性束流电力系统10秒运行分析
2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226396
C. Pawley, J. Scoville, R. Hong, T. Stevenson, G. Rossi, J. Edwards, A. von Halle
{"title":"Analysis of DIII-D neutral beam power systems for 10 second operation","authors":"C. Pawley, J. Scoville, R. Hong, T. Stevenson, G. Rossi, J. Edwards, A. von Halle","doi":"10.1109/FUSION.2009.5226396","DOIUrl":"https://doi.org/10.1109/FUSION.2009.5226396","url":null,"abstract":"The neutral beam injector systems on the DIII-D tokamak are currently limited to 3 seconds of total beam on time with the existing beam line components. To achieve high performance discharges with a high fraction of non-inductive neutral beam current drive for pulse lengths longer than the resistive time, long pulse upgrades are planned for both the neutral beam line and the power supplies that drive it. The beam on time will be extended to 10 seconds to provide full drive throughout the tokamak shot.","PeriodicalId":236460,"journal":{"name":"2009 23rd IEEE/NPSS Symposium on Fusion Engineering","volume":"10 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":"123686744","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: 2
Critical issues for disposal, recycling, and clearance of fusion radioactive materials: The European viewpoint 处置、回收和清除核聚变放射性物质的关键问题:欧洲观点
2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226497
M. Zucchetti, L. Di Pace, B. Kolbasov, V. Massaut
{"title":"Critical issues for disposal, recycling, and clearance of fusion radioactive materials: The European viewpoint","authors":"M. Zucchetti, L. Di Pace, B. Kolbasov, V. Massaut","doi":"10.1109/FUSION.2009.5226497","DOIUrl":"https://doi.org/10.1109/FUSION.2009.5226497","url":null,"abstract":"In order to maximize the environmental benefits of fusion power generation, it is important to clearly define the parameters governing the back-end of the materials cycle. A fusion-specific approach is necessary. Recycling of materials and clearance (i.e. declassification to non-radioactive material) are the two recommended options for reducing the amount of fusion waste, while the disposal as low-level waste could be an alternative route for specific materials and components. Most fusion materials could potentially be recycled or cleared, providing the necessary studies and developments are carried out. To enhance prospects for a successful waste management scheme, we identified the key issues and challenges for disposal, recycling, and clearance, focusing on the EU studies.","PeriodicalId":236460,"journal":{"name":"2009 23rd IEEE/NPSS Symposium on Fusion Engineering","volume":"32 11","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2009-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"120905804","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
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