2011 IEEE/NPSS 24th Symposium on Fusion Engineering最新文献_第8页

Proposal of electrical edge joint for a demountable high-temperature superconducting magnet 一种可拆卸高温超导磁体电边接头的设计

2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052302

S. Ito, H. Hashizume, L. Bromberg, M. Takayasu, J. Minervini

{"title":"Proposal of electrical edge joint for a demountable high-temperature superconducting magnet","authors":"S. Ito, H. Hashizume, L. Bromberg, M. Takayasu, J. Minervini","doi":"10.1109/SOFE.2011.6052302","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052302","url":null,"abstract":"Electrical edge joint of a stacked high-temperature superconducting (HTS) conductor is explored for electrical joints for a demountable HTS toroidal field coil. Demountable coils would be very useful in small tokamak plasma-facing component-test machines, such as Vulcan. The demountable concept consists of forcing together the edges of stacked HTS conductor embedded in a conductive or a structural material. Numerical evaluation showed that inserting an indium film between joint surfaces or plating copper layer on joint surfaces could prevent joint resistance from increasing due to misalignment of the contact surface and would provide a compliant layer between joints. Joint resistance of the edge joint can become smaller than that of electrical lap joint when the number of the stacked HTS tape is large. We carried out a testing program of the edge joint of a stacked YBCO conductor within a copper jacket. The HTS cable has a critical current of 1600 A at 77 K in self field. The experimental results showed that joint resistance in the edge joint was higher than expectation, as was irreproducible. One potential reason for the degradation of HTS material is the damage to the tape edge in preparation of the joint region due to milling. Another potential reason was low accuracy of fabrication of joint surface, the joint surface were not parallel to another one. The joint resistance will be reduced by sophistication of fabrication process for the joint surface.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"49 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2011-06-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"121323237","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

Development of CuCrZr alloy for applications in Neutral Beams 中性梁用CuCrZr合金的研制

2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052213

C. Rotti, A. Chakraborty, I. Ahmed, G. Roopesh, M. Bandyopadhyay, M.J. Singh, Sejal Shah, A. Phukan, R. Yadav, N. Panda, K. Balasubramanian

引用次数: 4

Fusion for neutrons: A realisable fusion neutron source 中子聚变:一种可实现的聚变中子源

2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052205

A. Sykes, M. Gryaznevich, G. Voss, D. Kingham, B. Kuteev

{"title":"Fusion for neutrons: A realisable fusion neutron source","authors":"A. Sykes, M. Gryaznevich, G. Voss, D. Kingham, B. Kuteev","doi":"10.1109/SOFE.2011.6052205","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052205","url":null,"abstract":"For 60 years fusion research has been focused on Fusion for Energy (F4E) as the ultimate carbon-free solution to the world's energy problems. It is proving a worthy but difficult task. However it is relatively easy to produce high-energy fusion neutrons. The many potential applications of a 14MeV neutron source are outlined, and a range of existing designs for such a source, based on a D-T fuelled Spherical Tokamak (ST), are reviewed. It is shown that the problems of high build and operating costs and uncertainties in operating conditions, can be eased by a small device SCFNS (Super-Compact Fusion Neutron Source) of major radius ∼0.5m, which although operating at modest plasma performance can provide megawatt-level neutron output. This break-through is achieved via the effectiveness of beam-plasma fusion, which becomes dominant in these conditions. Such a device would provide a resolution of the uncertainties in fusion STs (such as start-up, ramp-up, and steady-state operation); be an effective neutron source for research, and be an ideal entry vehicle for development of more powerful neutron sources in the new objective of ‘Fusion for Neutrons’ (F4N).","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"16 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2011-06-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"125739373","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

The influence of injector design on neutral beam optimisation for DEMO 注入器设计对DEMO中性束优化的影响

2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052258

E. Surrey, A. Benn, I. Jenkins, M. Porton, W. Timmis

引用次数: 0

ITER diagnostic challenges ITER诊断挑战

2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052210

M. Walsh, P. Andrew, R. Barnsley, L. Bertalot, R. Boivin, D. Bora, R. Bouhamou, S. Ciattaglia, A. Costley, G. Counsell, M. Direz, J. Drevon, A. Encheva, T. Fang, M. von Hellermann, D. Johnson, J. Kim, Y. Kusama, H. G. Lee, B. Levesy, A. Martin, P. Maquet, K. Okayama, R. Reichle, K. Patel, C. S. Pitcher, A. Prakash, S. Simrock, N. Taylor, V. Udintsev, Y. Utin, P. Vasu, G. Vayakis, E. Veshchev, B. Schunke, C. Walker, C. Watts, A. Zvonkov

引用次数: 22

Overvoltage protection of the Ion source and extraction power supplies in the SPIDER experiment SPIDER实验中离子源和萃取电源的过电压保护

2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052346

A. Zamengo, A. Pesce, M. Bigi

引用次数: 2

Numerical calculation of reactions on electrode surfaces and in a volume of a discharge type fusion neutron source 放电型聚变中子源电极表面和体积内反应的数值计算

2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052315

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

引用次数: 0

Fusion Nuclear Science Facility (FNSF) 聚变核科学设施(FNSF)

2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052222

Y-K.M. Peng, J.M. Park, J. Canik, S. Diem, A. Sontag, A. Lumsdaine, Yl Katoh, R. Burgess, K. Korsah, B. Patton, J. Wagner, P. Fogarty, M. Sawan

{"title":"Fusion Nuclear Science Facility (FNSF)","authors":"Y-K.M. Peng, J.M. Park, J. Canik, S. Diem, A. Sontag, A. Lumsdaine, Yl Katoh, R. Burgess, K. Korsah, B. Patton, J. Wagner, P. Fogarty, M. Sawan","doi":"10.1109/SOFE.2011.6052222","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052222","url":null,"abstract":"A compact (R0∼1.2–1.3m), low aspect ratio, low-Q (<3) Fusion Nuclear Science Facility (FNSF) was recently assessed to provide a fully integrated, D-T-fueled, continuously driven plasma, volumetric nuclear environment of copious neutrons. This environment would be used, for the first time, to carry out discovery-driven research in fusion nuclear science and materials, in parallel with and complementary to ITER. This research would aim to test, discover, and understand new nuclear-nonnuclear synergistic interactions involving plasma material interactions, neutron material interactions, tritium fuel breeding and transport, and power extraction, and innovate and develop solutions for DEMO components. This facility properly designed could provide, initially using conservative JET-level D-T plasmas in Hot-Ion H-Mode, and an outboard fusion neutron flux of ∼0.33 MW/m2. If the research, facility operation, and component solutions were successful, the performance could be raised to 1 MW/m2 (fusion power ∼76 MW) by reaching for twice the JET plasma pressure and Q. Stable high-safety factor q and ² plasmas would be chosen to minimize plasma-induced disruptions, and deliver reliably a neutron fluence of 1 MW-yr/m2, if duty factors of ∼10% (accumulated plasma burn time in a year) can be achieved. Such duty factors would therefore require time-efficient installation and replacement of all components using remote handling (RH). These in turn would require RH-compatible modular designs for all internal components, a single-turn toroidal field coil center-post, and placement of support structures and vacuum seal welds behind the internal and shielding components. RH-enabled hot-cell laboratories would enable preparation and investigations of damages of the internal test components. The scientific and technical basis for such an FNSF, and the research needed in the next decade to manage the potential risks in its research capabilities, will be described.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"30 2","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2011-06-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"114006183","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

NSTX Power Supply configuration control upgrade NSTX电源配置控制升级

2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052335

N. Desai, R. Hatcher, C. Neumeyer

引用次数: 0

Thermalhydraulic optimization of hypervapotron geometries for first wall applications 首次应用于壁的超蒸汽管几何形状的热工优化

2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052283

D. Youchison, M. Ulrickson, J. Bullock

引用次数: 2