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

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Performance study of non-contact surface measurement technology for use in an experimental fusion device 实验核聚变装置非接触面测量技术的性能研究
2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1117/12.825267
A. Brownhill, S. Robson, R. Brade
{"title":"Performance study of non-contact surface measurement technology for use in an experimental fusion device","authors":"A. Brownhill, S. Robson, R. Brade","doi":"10.1117/12.825267","DOIUrl":"https://doi.org/10.1117/12.825267","url":null,"abstract":"To supplement existing metrology techniques EFDA-JET has been investigating non-contact surface scanning of plasma facing components during shutdown periods. Research has been focusing on commercially available technologies capable of remote handling, assessing their abilities against common artefacts with features and surface representative of new first wall protection tiles.","PeriodicalId":236460,"journal":{"name":"2009 23rd IEEE/NPSS Symposium on Fusion Engineering","volume":"65 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":"121700402","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: 8
ITER ICRF system: R&D progress and technical choices ITER ICRF系统:研发进展与技术选择
2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226425
B. Beaumont, T. Gassmann, F. Kazarian, P. Lamalle, A. Mukherjee, U. Baruah, D. Rasmussen, R. Sartori
{"title":"ITER ICRF system: R&D progress and technical choices","authors":"B. Beaumont, T. Gassmann, F. Kazarian, P. Lamalle, A. Mukherjee, U. Baruah, D. Rasmussen, R. Sartori","doi":"10.1109/FUSION.2009.5226425","DOIUrl":"https://doi.org/10.1109/FUSION.2009.5226425","url":null,"abstract":"This paper describes the ITER ICRF system main requirements and the latest developments for its different parts which are to be procured by the ITER Parties. The built in margins will allow reaching the requirements on a large parameter range, or delivering more power in a restricted range.","PeriodicalId":236460,"journal":{"name":"2009 23rd IEEE/NPSS Symposium on Fusion Engineering","volume":"278 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":"121824314","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
Mechanical design of the NSTX Liquid Lithium Divertor NSTX液体锂分流器的机械设计
2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226433
R. Ellis, R. Kaita, H. Kugel, G. Paluzzi, M. Viola, R. Nygren
{"title":"Mechanical design of the NSTX Liquid Lithium Divertor","authors":"R. Ellis, R. Kaita, H. Kugel, G. Paluzzi, M. Viola, R. Nygren","doi":"10.1109/FUSION.2009.5226433","DOIUrl":"https://doi.org/10.1109/FUSION.2009.5226433","url":null,"abstract":"The Liquid Lithium Divertor (LLD) on NSTX will be the first test of a fully-toroidal liquid lithium divertor in a high-power magnetic confinement device. It will replace part of the lower outboard divertor between a specified inside and outside radius, and ultimately provide a lithium surface exposed to the plasma with enough depth to absorb a significant particle flux.","PeriodicalId":236460,"journal":{"name":"2009 23rd IEEE/NPSS Symposium on Fusion Engineering","volume":"112 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":"114954357","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
Advancements in electrical insulations for fusion devices 核聚变装置电绝缘的进展
2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226460
M. Madhukar, B. Morgan, J. Walsh, M. Hooker
{"title":"Advancements in electrical insulations for fusion devices","authors":"M. Madhukar, B. Morgan, J. Walsh, M. Hooker","doi":"10.1109/FUSION.2009.5226460","DOIUrl":"https://doi.org/10.1109/FUSION.2009.5226460","url":null,"abstract":"The cyanate ester polymer, CTD 403, is being considered for use as an insulation material in future fusion devices. In this study, the moisture resistance of neat polymer, glass fiber/CTD 403 and copper foil/CTD 403 was studied. The results show that while prolonged exposure to moisture cause property degradation, however, most of the property loss is recovered after drying the specimens.","PeriodicalId":236460,"journal":{"name":"2009 23rd IEEE/NPSS Symposium on Fusion Engineering","volume":"56 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":"115379174","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
Compensation of beamlet deflection by mechanical offset of the grids apertures in the SPIDER ion source 蜘蛛离子源中网格孔径的机械偏移补偿激光束偏转
2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226537
P. Agostinetti, V. Antoni, N. Pilan, G. Serianni
{"title":"Compensation of beamlet deflection by mechanical offset of the grids apertures in the SPIDER ion source","authors":"P. Agostinetti, V. Antoni, N. Pilan, G. Serianni","doi":"10.1109/FUSION.2009.5226537","DOIUrl":"https://doi.org/10.1109/FUSION.2009.5226537","url":null,"abstract":"The SPIDER experiment has the main goal to test the extraction of negative ions from an ITER size ion source. It is designed to extract 1280 negative ion beamlets and accelerate them up to a 100 kV potential. The negative ion beam at exit and the operating parameters will be carefully measured and optimized in order to match the ITER requirements for the NBI (Neutral Beam Injector) ion sources. Inside a negative ion accelerator, there are generally two main factors that can cause deflection of the ion beamlets: the repulsion among beamlets and the electron suppression magnetic field. These two effects are both to be considered highly detrimental for the ITER NBI, as they are expected to cause higher heat loads on the ITER NBI neutralizer and decrease the overall beam quality (in terms of aiming and divergence). Hence they should be considered and minimized also for the SPIDER device, where it will be possible to precisely investigate the beamlet footprint using an instrumented calorimeter relatively close to the accelerator exit. This paper presents a design optimization process aiming at compensating the two described effects. To make this, a mechanical offset of the grounded grid apertures is considered. The OPERA-3d code (Vector Fields Co. Ltd.) is used as the main tool for this optimization process, as it can take into account the beamlet repulsion and the interaction between beamlets and grids. This is made by solving the electrostatic Poisson's equation with a finite element approach, to calculate the particle trajectories of the negative ions under the influence of electrostatic fields, magnetic fields and space charge.","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":"123309914","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
Target steering and electrostatic acceleration for IFE IFE的目标转向和静电加速
2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226377
R. Petzoldt, D. Goodin, E. Valmianski, L. Carlson, J. Stromsoe, J. Hares
{"title":"Target steering and electrostatic acceleration for IFE","authors":"R. Petzoldt, D. Goodin, E. Valmianski, L. Carlson, J. Stromsoe, J. Hares","doi":"10.1109/FUSION.2009.5226377","DOIUrl":"https://doi.org/10.1109/FUSION.2009.5226377","url":null,"abstract":"We have demonstrated that in-flight electrostatic steering can substantially improve target placement accuracy. We optically track the motion of a charged target and feed back appropriate steering voltage to four steering electrodes. Target placement accuracy of falling ∼1.8 mg shells with 0.5 m stand off from steering electrodes is improved from ∼ 500 to 10 µm standard deviation in each transverse direction. It might be possible to replace current-day positioning systems for target shots with a system such as this, resulting in substantial debris reduction. We also completed fabrication and started testing an electrostatic accelerator that advances the electric field each time the charged target passes one of the 96 accelerating electrodes. Many of the accelerating electrodes are segmented to allow transverse position correction based on transverse position measurements during the acceleration process. The accelerator operation has now transitioned to vacuum acceleration of 1.8 mg hollow shells. Calculations indicate that this “first step” accelerator could achieve 10–15 m/s target velocity in 0.9 m with −0.5 nC target charge and ±4 kV accelerating voltage. Demonstrating this capability is still underway. Additional experimental work and updated acceleration results will be presented.","PeriodicalId":236460,"journal":{"name":"2009 23rd IEEE/NPSS Symposium on Fusion Engineering","volume":"1 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":"128658075","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
Thermo-mechanical analysis of a prototypical SiC foam-based flow channel insert 碳化硅泡沫基流道嵌件原型的热力学分析
2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226527
S. Sharafat, A. Aoyama, N. Morley, N. Ghoniem, B. Williams, Y. Katoh
{"title":"Thermo-mechanical analysis of a prototypical SiC foam-based flow channel insert","authors":"S. Sharafat, A. Aoyama, N. Morley, N. Ghoniem, B. Williams, Y. Katoh","doi":"10.1109/FUSION.2009.5226527","DOIUrl":"https://doi.org/10.1109/FUSION.2009.5226527","url":null,"abstract":"As part of the US ITER Test Blanket Module development effort several FCI concepts using a variety of porous SiC and SiC/SiC composites are being developed. In this work we report on the thermo-mechanical analysis of a SiC foam-based FCI. Prototypes of FCI segments as large as 0.12 m × 0.75 m × 0.015 m were recently fabricated and heat tested with a maximum ΔT of ∼150 °C across the FCI walls. No visible damage was observed after testing. A detailed thermo-mechanical analysis of the test was conducted and results of the simulations are discussed in context of actual FCI operating conditions.","PeriodicalId":236460,"journal":{"name":"2009 23rd IEEE/NPSS Symposium on Fusion Engineering","volume":"66 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":"125409686","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
Conceptual design of optical path related elements in the port plug of ITER core lidar diagnostic ITER核心激光雷达诊断端口插头中光程相关元件的概念设计
2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226478
B. Mészáros, G. Porempovics, M. Walsh
{"title":"Conceptual design of optical path related elements in the port plug of ITER core lidar diagnostic","authors":"B. Mészáros, G. Porempovics, M. Walsh","doi":"10.1109/FUSION.2009.5226478","DOIUrl":"https://doi.org/10.1109/FUSION.2009.5226478","url":null,"abstract":"The present paper describes the engineering conceptual design of the optical labyrinth and the first and second mirror mounts of the ITER core LIDAR diagnostics. The optical labyrinth, being in a very sensitive location close and open to the plasma, has been examined carefully to be able to provide different solutions satisfying the needs of the diagnostics. Therefore the conceptual design considered the covering of the light path, the integration of the labyrinth into the port plug as well as the shape, color and material of the labyrinth inner surface to be able to handle the undesirable phenomena of scattered light and sputtered particles reaching the mirroring surface. Nevertheless, cooling/ baking has also been considered and appropriate solutions presented.","PeriodicalId":236460,"journal":{"name":"2009 23rd IEEE/NPSS Symposium on Fusion Engineering","volume":"19 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":"128567839","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
Plasma facing conponents of EAST EAST的等离子体面成分
2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226435
Y. Song, H. Xie, X. Liu, L. Bao, Z. Zhou, L. Cao, T. Xu, X. Peng, Y. Peng, N. Zhu, P. Zhang, J. Wu, S. Wang, X. Wang, J. Hu, J. Chen, G. Luo, D. Yao, D. Gao, P. Fu, J. Li
{"title":"Plasma facing conponents of EAST","authors":"Y. Song, H. Xie, X. Liu, L. Bao, Z. Zhou, L. Cao, T. Xu, X. Peng, Y. Peng, N. Zhu, P. Zhang, J. Wu, S. Wang, X. Wang, J. Hu, J. Chen, G. Luo, D. Yao, D. Gao, P. Fu, J. Li","doi":"10.1109/FUSION.2009.5226435","DOIUrl":"https://doi.org/10.1109/FUSION.2009.5226435","url":null,"abstract":"EAST plasma facing components (PFCs) have the function of protecting the vacuum vessel, heating systems and diagnostic components from the plasma particles and heat loads, and also additional to this particles and heat loads handling. They are installed in the vacuum vessel together with in-vessel coils, cryopump and diagnostic components. The design, fabrication and assembly have been finished. The PFCs are designed up-down symmetry to accommodate with both double null and single null plasma configuration. All PFCs use graphite tile for plasma facing surfaces affixed to copper alloy heat sink. A special deep hole drilling technology was developed to drill cooling channels directly on heat sink for high efficient heat removal. All Heat sink are installed onto the base alignment rails through stainless steel supports. As the benchmark of assembly for PFCs, the base rails are installed and measured precise based on a new alignment method integrating the optical instruments and a mechanical template. And so is a mechanical check template for checking the surface of first wall. As indicated, all the first wall components were fabricated and assembled successfully and meet the design requirement for the plasma operation.","PeriodicalId":236460,"journal":{"name":"2009 23rd IEEE/NPSS Symposium on Fusion Engineering","volume":"144 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":"124627663","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
Copper alloys used for support units of ITER blanket modules: Compression and tension properties ITER包层模块支撑单元用铜合金:压缩和拉伸性能
2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226503
G. Kalinin, Y. Strebkov, N. S. Krestnikov, E. V. Parshutin
{"title":"Copper alloys used for support units of ITER blanket modules: Compression and tension properties","authors":"G. Kalinin, Y. Strebkov, N. S. Krestnikov, E. V. Parshutin","doi":"10.1109/FUSION.2009.5226503","DOIUrl":"https://doi.org/10.1109/FUSION.2009.5226503","url":null,"abstract":"Four flexible support units are used for each first wall module bracing to the vacuum vessel of ITER. The support unit consists of fastening bolt, flexible cartridge and collar for compensation of thermal expansion. The collar made of copper alloy operates under considerable compression load. The performed structural analysis shows that stresses in the collar exceed the design allowable value specified in ITER Structural Design Criteria for In-Vessel components (SDC-IG) for CuCrZr-IG alloy. The ITER SDC-IC design allowables for CuCrZr-IG alloy were based on tensile data for solution annealed and age material. There is a potential to keep structural integrity if material with higher strength will be used. It is also reasonable to use real compression data for specification of allowable stresses.","PeriodicalId":236460,"journal":{"name":"2009 23rd IEEE/NPSS Symposium on Fusion Engineering","volume":"115 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":"124679285","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
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