2009 23rd IEEE/NPSS Symposium on Fusion Engineering最新文献_第10页

Metrology techniques for the assembly of NCSX NCSX装配的计量技术

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226516

C. Priniski, T. Dodson, M. Duco, S. Raftopoulos, R. Ellis, A. Brooks

{"title":"Metrology techniques for the assembly of NCSX","authors":"C. Priniski, T. Dodson, M. Duco, S. Raftopoulos, R. Ellis, A. Brooks","doi":"10.1109/FUSION.2009.5226516","DOIUrl":"https://doi.org/10.1109/FUSION.2009.5226516","url":null,"abstract":"In support of the National Compact Stellerator Experiment (NCSX), stellerator assembly activities continued this past year at the Princeton Plasma Physics Laboratory (PPPL) in partnership with the Oak Ridge National Laboratory (ORNL). The construction program saw the completion of the first two Half Field-Period Assemblies (HPA), each consisting of three modular coils. The full machine includes six such sub-assemblies. A single HPA consists of three of the NCSX modular coils wound and assembled at PPPL. These geometrically-complex three-dimensional coils were wound using computer-aided metrology and CAD models to tolerances within +/−- 0.5mm. The assembly of these coils required similar accuracy on a larger scale with the added complexity of more individual parts and fewer degrees of freedom for correction. Several new potential positioning issues developed for which measurement and control techniques were developed. To accomplish this, CAD coordinate-based computer metrology equipment and software similar to the solutions employed for winding the modular coils was used. Given the size of the assemblies, the primary tools were both interferometeraided and Absolute Distance Measurement (ADM)-only based laser trackers. In addition, portable Coordinate Measurement Machine (CMM) arms and some novel indirect measurement techniques were employed. This paper will detail both the use of CAD coordinate-based metrology technology and the techniques developed and employed for dimensional control of NSCX sub-assemblies. The results achieved and possible improvements to techniques will be discussed.","PeriodicalId":236460,"journal":{"name":"2009 23rd IEEE/NPSS Symposium on Fusion Engineering","volume":"30 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":"125964170","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

Massive pellet and rupture disk testing for disruption mitigation applications 用于减少破坏应用的大颗粒和破裂盘测试

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226512

S. Combs, S. Meitner, L. Baylor, J. Caughman, N. Commaux, D. Fehling, C. Foust, T. Jernigan, J. McGill, P. Parks, D. Rasmussen

{"title":"Massive pellet and rupture disk testing for disruption mitigation applications","authors":"S. Combs, S. Meitner, L. Baylor, J. Caughman, N. Commaux, D. Fehling, C. Foust, T. Jernigan, J. McGill, P. Parks, D. Rasmussen","doi":"10.1109/FUSION.2009.5226512","DOIUrl":"https://doi.org/10.1109/FUSION.2009.5226512","url":null,"abstract":"Injection of massive quantities of noble gases or D2 has proven to be effective at mitigating some of the deleterious effects of disruptions in tokamaks. Two alternative methods that might offer some advantages over the present technique for massive gas injection are “shattering” massive pellets and employing close-coupled rupture disks. Laboratory testing has been carried out to evaluate their feasibility. For the study of massive pellets, a pipe gun pellet injector cooled with a cryogenic refrigerator was fitted with a relatively large barrel (16.5 mm bore), and D2 and Ne pellets were made and were accelerated to speeds of ∼600 and 300 m/s, respectively. Based on the successful proof-of-principle testing with the injector and a special double-impact target to shatter pellets, a similar system has been prepared and installed on DIII-D and should be ready for experiments later this year. To study the applicability of rupture disks for disruption mitigation, a simple test apparatus was assembled in the lab. Commercially available rupture disks of 1 in. nominal diameter were tested at conditions relevant for the application on tokamaks, including tests with Ar and He gases and rupture pressures of ∼54 bar. Some technical and practical issues of implementing this technique on a tokamak are discussed.","PeriodicalId":236460,"journal":{"name":"2009 23rd IEEE/NPSS Symposium on Fusion Engineering","volume":"69 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":"125181502","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

Toroidally rotating plasma confinement with a spatially periodic field 具有空间周期场的环形旋转等离子体约束

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226398

C. Ordonez

引用次数: 1

Plasma and current drive parameter options for a megawatt range fusion neutron source 兆瓦级聚变中子源的等离子体和电流驱动参数选择

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226382

B. Kuteev, A. Borisov, A. Golikov, V. Khripunov, V. Lukash, E. Popova, P. Savrukhin, P. Goncharov, V. Sergeev, M. Gryaznevich

引用次数: 3

Multi-purpose fiber optic sensors for high temperature superconducting magnets 多用途高温超导磁体光纤传感器

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226397

M. Turenne, R. Johnson, F. Hunte, J. Schwartz, H. Song

引用次数: 20

Performance issues for actuators and internal components during long pulse operation Tore Supra experience 执行器和内部组件在长脉冲操作期间的性能问题

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226530

J. Bucalossi

引用次数: 1

Design of plasma shape control system for KSTAR tokamak KSTAR托卡马克等离子体形状控制系统设计

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226524

S. Hahn, J.H. Choi, J.K. Jin, Y. Jeon, S. Yoon, J. Kim, Y. Bae, M. Park, K.R. Park, Y.S. Kim, H. Yang, W. Kim, Y. Oh, M. Kwon, M. Walker, D. Humphreys, B. Penaflor, D. Piglowski, R. Johnson, A. Welander, J. Leuer, N. Eidietis, A. Hyatt, G. Jackson, D. Mueller

{"title":"Design of plasma shape control system for KSTAR tokamak","authors":"S. Hahn, J.H. Choi, J.K. Jin, Y. Jeon, S. Yoon, J. Kim, Y. Bae, M. Park, K.R. Park, Y.S. Kim, H. Yang, W. Kim, Y. Oh, M. Kwon, M. Walker, D. Humphreys, B. Penaflor, D. Piglowski, R. Johnson, A. Welander, J. Leuer, N. Eidietis, A. Hyatt, G. Jackson, D. Mueller","doi":"10.1109/FUSION.2009.5226524","DOIUrl":"https://doi.org/10.1109/FUSION.2009.5226524","url":null,"abstract":"The development of the plasma shape control system of the Korea Superconducting Tokamak and Advanced Research (KSTAR) continues from the first utilization for plasma current/ major radii to the full-scale utilizations of the poloidal superconducting magnets and the in-vessel stabilization coils for the highly elongated (κ ∼ 2.0) plasmas planned in 2009/2010. In this paper the shape control of KSTAR is analyzed as a complete integrated form, including the operation design and experiences. In the first plasma campaign held in 2008, the plasma shape control system has been prepared as part of the pulse operation controls for the first daily operation. A time-synchronized shot sequence supervisions and actuator integrations has been done by the full-digital centralization scheme via the EPICS communicating layers and the dedicated fast communication layers. In the end a reliable real-time plasma feedback system have been accomplished for making/sustaining plasma current and major radius. The status of the shape control upgrade proposed for upcoming years is shown as well as the actuator control developments and the newly-introduced in-vessel vertical stabilization control scheme.","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":"115337552","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

Numerical analysis of forced convection heat transfer in first wall rib-roughened channels for liquid lithium lead blanket 液锂铅包层第一壁肋粗化通道强制对流换热数值分析

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226437

Wei‐Hong Wang, Desheng Cheng, Yunqing Bai, Songlin Liu, Xi Pei

{"title":"Numerical analysis of forced convection heat transfer in first wall rib-roughened channels for liquid lithium lead blanket","authors":"Wei‐Hong Wang, Desheng Cheng, Yunqing Bai, Songlin Liu, Xi Pei","doi":"10.1109/FUSION.2009.5226437","DOIUrl":"https://doi.org/10.1109/FUSION.2009.5226437","url":null,"abstract":"The first wall as the key component of the liquid metal blanket must withstand and remove the maximum heat flux from the plasma chamber and high power density LiPb breeder zone. A suitable countermeasure would be artificial roughening of the coolant channel wall facing the plasma for intensifying heat exchange. The rib-roughened coolant channels with high pressure helium gas for FDS series liquid lithium lead blanket were designed to enhance the turbulence heat transfer in comparison with smooth coolant channels. Heat transfer coefficients and friction factors in rib-roughened coolant channels of the first wall are investigated using the computational fluid dynamics code FLUENT??based on the two dimensional physical model and periodic condition. From the results of the numerical analysis, the turbulence heat transfer Nusselt number (Nu) in the rectangular channels of rib-roughened face is higher 200% than those in the smooth channels, and the fraction coefficient (ƒ) between the helium gas and CLAM steel structure is 20% more than those in the smooth channels. The numerically optimized parameters are also presented considering different convexity part height and width as well.","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":"115375468","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

Generation of neutron beam by the cylindrical discharge fusion device 圆柱形放电聚变装置产生中子束

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226383

T. Kanagae, K. Noborio, Y. Yamamoto, S. Konishi

引用次数: 6

Jet operations and plasma control: A plasma control system that is safe and flexible in a manageable way. 射流操作和等离子体控制:等离子体控制系统安全、灵活、易于管理。

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226522

F. Sartori, T. Budd, P. Card, R. Felton, P. Lomas, P. Mccullen, F. Piccolo, L. Zabeo, R. Albanese, G. Ambrosino, G. De Tommasi, A. Pironti

引用次数: 6