2009 23rd IEEE/NPSS Symposium on Fusion Engineering最新文献_第2页

He-cooled divertor for DEMO: Technological studies and experimental verification of the design 演示用氦冷分流器:设计的技术研究和实验验证

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226529

P. Norajitra, S. Antusch, H. Ritzhaupt‐Kleissl, L. Spatafora, V. Widak, R. Giniyatulin, V. Kuznetsov, I. Mazul, I. Ovchinnikov

{"title":"He-cooled divertor for DEMO: Technological studies and experimental verification of the design","authors":"P. Norajitra, S. Antusch, H. Ritzhaupt‐Kleissl, L. Spatafora, V. Widak, R. Giniyatulin, V. Kuznetsov, I. Mazul, I. Ovchinnikov","doi":"10.1109/FUSION.2009.5226529","DOIUrl":"https://doi.org/10.1109/FUSION.2009.5226529","url":null,"abstract":"A modular He-cooled divertor concept for DEMO is being investigated at Forschungszentrum Karlsruhe (FZK) within the framework of the EU power plant conceptual study. The design goal is to reach a heat flux of at least 10 MW/m2. The reference divertor design is based on the use of a tungsten tile which is brazed to a thimble made of W-1wt%La2O3 cooled by helium impingement jets. The current divertor work programme focuses on manufacture and high-heat-flux tests of prototypical tungsten mock-ups to demonstrate the manufacturability and the performance of the design. Till now three high-heat-flux test series on 1-finger mock-ups were successfully performed in a combined helium loop and TSEFEY facility at Efremov. Technological study on fabrication of a 9-finger module of stain less steel was carried out. First gas flow tests showed uniform mass flow rate distribution which agrees well with calculation results. These initial test results confirm the performance of this concept and serve as a strong basis for further development of the material and concept and more integrated testing.","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":"126497959","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

Tritium transport finite element modeling tools for breeding blanket design 氚输运有限元建模工具用于育种毯设计

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226403

S. Terron, C. Moreno, L. Sedano, F. Gabriel, A. Abánades

引用次数: 0

Beryllides for fusion reactors 核聚变反应堆用铍化物

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226458

J. Reimann, P. Kurinskiy, R. Lindau, A. Moeslang, M. Rohde, C. Dorn, W. Haws, A. Goraieb, H. Harsch, C. Linsmeier

引用次数: 3

NCSX Trim Coil design NCSX修剪线圈设计

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226452

M. Kalish, A. Brooks, J. Rushinski, R. Upcavage

{"title":"NCSX Trim Coil design","authors":"M. Kalish, A. Brooks, J. Rushinski, R. Upcavage","doi":"10.1109/FUSION.2009.5226452","DOIUrl":"https://doi.org/10.1109/FUSION.2009.5226452","url":null,"abstract":"The National Compact Stellarator Experiment (NCSX) was being constructed at the Princeton Plasma Physics Laboratory in partnership with Oak Ridge National Laboratory before work was stopped in 2008. The objective of this experiment was to develop the stellarator concept and evaluate it's potential as a model for future fusion power plants. Stellarator design requires very precisely positioned Modular Coils of complex shape to form 3D plasmas. In the design of NCSX, Trim Coils were required to compensate for both the positioning of the coils during assembly and the fabrication tolerances of the Modular Coils. Use of the Trim Coils allowed for larger tolerances increasing ease of assembly and decreasing overall cost. A set of Trim coils was developed to suppress the toroidal flux in island regions due to misalignment, magnetic materials, and eddy currents. The requirement imposed upon the design forced the toroidal flux in island regions below 10% of the total toroidal flux in the plasma. An analysis was first performed to evaluate candidate Trim Coil configurations iterating both the size, number, and position of the coils. The design was optimized considering both performance and cost while staying within the tight restraints presented by the space limited geometry. The final design of the Trim Coils incorporated a 48 Coil top bottom symmetric set. Fabrication costs were minimized by having only two coil types and using a planar conventional design with off the shelf commercial conductor. The Trim Coil design incorporated supports made from simple structural shapes assembled together in a way which allowed for adjustment as well as accommodation for the tolerance build up on the mating surfaces. This paper will summarize the analysis that led to the optimization of the Trim Coils set, the trim coil mechanical design, thermal and stress analysis, and the design of the supporting Trim Coil structure.","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":"130876651","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

Engineering cost & schedule lessons learned on NCSX 在NCSX上获得的工程成本和进度经验教训

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226449

R. Strykowsky, T. Brown, J. Chrzanowski, M. Cole, P. Heitzenroeder, G. Neilson, D. Rej, M. Viol

{"title":"Engineering cost & schedule lessons learned on NCSX","authors":"R. Strykowsky, T. Brown, J. Chrzanowski, M. Cole, P. Heitzenroeder, G. Neilson, D. Rej, M. Viol","doi":"10.1109/FUSION.2009.5226449","DOIUrl":"https://doi.org/10.1109/FUSION.2009.5226449","url":null,"abstract":"The National Compact Stellarator Experiment (NCSX) is designed to test physics principles of an innovative stellarator design developed by the Princeton Plasma Physics Laboratory (PPPL) and Oak Ridge National Laboratory (ORNL). The project was technically very challenging, primarily due to the complex component geometries and tight tolerances that were required. As the project matured these challenges manifested themselves through all phases of the project (i.e. design, R&D, fabrication and assembly). Although the project was not completed, several major work packages, comprising about 65% of the total estimated cost (excluding management and contingency), were completed, providing a data base of actual costs that can be analyzed to understand cost drivers. Technical factors that drove costs included the complex geometry, tight tolerances, material requirements, and performance requirements. Management factors included imposed annual funding constraints that throttled project cash flow, staff availability, and inadequate R&D. Understanding how requirements and design decisions drove cost through this top-down forensic cost analysis could provide valuable insight into the configuration and design of future Stellarators and other devices.","PeriodicalId":236460,"journal":{"name":"2009 23rd IEEE/NPSS Symposium on Fusion Engineering","volume":"43 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":"132183474","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: 24

Thermo-mechanical analysis of a W-Ta-ODS divertor transition joint W-Ta-ODS导流器过渡接头的热-力学分析

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226428

S. Sharafat, A. Aoyama, N. Ghoniem, J. Blanchard, S. Malang

引用次数: 4

Siting evaluations for the ignitor fusion experiment: Preliminary radiological assessments 点火器融合实验的选址评估:初步放射学评估

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226384

M. Zucchetti, L. Bonavigo, F. Franza, M. Caldarella, F. Chiaravalli, F. Mancini, G. Faelli, A. Ciampichetti, F. Bombarda, B. Coppi

引用次数: 0

Baseline system design and prototyping for the ITER high-frequency magnetic diagnostics set ITER高频磁诊断装置的基线系统设计和原型设计

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226481

D. Testa, R. Chavan, J. Guterl, J. Lister, J. Moret, A. Perez, F. Sanchez, B. Schaller, G. Tonetti, M. Toussaint, A. Encheva, G. Vayakis, C. Walker, Y. Fournier, T. Maeder, H. Carfantan

引用次数: 8

Embedding linux On FPGA: An application on a real-time neutron/gamma Discrimination system for fusion devices 在FPGA上嵌入linux:在核聚变装置中子/伽马实时识别系统中的应用

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226463

M. Riva, B. Esposito, D. Marocco, F. Belli

引用次数: 2

Low distortion welded joints for NCSX* 低变形焊接接头NCSX*

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226445

M. Denault, M. Viola, W. England

{"title":"Low distortion welded joints for NCSX*","authors":"M. Denault, M. Viola, W. England","doi":"10.1109/FUSION.2009.5226445","DOIUrl":"https://doi.org/10.1109/FUSION.2009.5226445","url":null,"abstract":"The National Compact Stellarator Experiment (NCSX) required precise positioning of the field coils in order to generate suitable magnetic fields. A set of three modular field coils were assembled to form the Half Field-Period Assemblies (HPA). Final assembly of the HPA required a welded shear plate to join individual coils in the nose region due to the geometric limitations and the strength constraints. Each of the modular coil windings was wound on a stainless steel alloy (Stellalloy) casting. The alloy is similar to austenitic 316 stainless steel. During the initial welding trials, severe distortion, of approximately 1/16″, was observed in the joint caused by weld shrinkage. The distortion was well outside the requirements of the design. Solutions were attempted through several simultaneous routes. The joint design was modified, welding processes were changed, and specialized heat reduction techniques were utilized. A final joint design was selected to reduce the amount of weld material needed to be deposited, while maintaining adequate penetration and strength. Several welding processes and techniques using Miller Axcess equipment were utilized that significantly reduced heat input. The final assembly of the HPA was successful. Distortion was controlled to 0.012″, well within the acceptable design tolerance range of 0.020″ over a 3.5 foot length.","PeriodicalId":236460,"journal":{"name":"2009 23rd IEEE/NPSS Symposium on Fusion Engineering","volume":"60 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":"115021725","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