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2011 IEEE/NPSS 24th Symposium on Fusion Engineering最新文献

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Optimized bends and mode filters for the main Transmission Lines of an ITER-relevant LHCD system iter相关LHCD系统主传输线弯曲和模式滤波器的优化
2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052317
F. Mirizzi, S. Ceccuzzi
{"title":"Optimized bends and mode filters for the main Transmission Lines of an ITER-relevant LHCD system","authors":"F. Mirizzi, S. Ceccuzzi","doi":"10.1109/SOFE.2011.6052317","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052317","url":null,"abstract":"To limit the transmission losses, Main Transmission Lines (MTL) for high power LHCD systems are usually realized by moderately oversized circular waveguides transmitting the low losses TE°01 mode. Bends in smooth circular waveguides generate spurious modes that must be limited in number and amplitude to avoid potentially destructive damages deriving from their trapping into the MTL. Optimized bends and effective mode filters have been studied to reduce this risk.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"34 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":"126689981","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
Newly developed innovative manufacturing technologies for He-cooled DEMO divertor 新开发的he冷却DEMO转喷器创新制造技术
2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052260
P. Norajitra, S. Antusch, W. Basuki, L. Spatafora, V. Toth
{"title":"Newly developed innovative manufacturing technologies for He-cooled DEMO divertor","authors":"P. Norajitra, S. Antusch, W. Basuki, L. Spatafora, V. Toth","doi":"10.1109/SOFE.2011.6052260","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052260","url":null,"abstract":"A modular He-cooled divertor concept for DEMO has been developed at Karlsruhe Institute of Technology (KIT). The design goal is to achieve a DEMO-relevant high heat flux of 10 MW/m2. The reference design HEMJ (He-cooled modular divertor with multiple-jet cooling) uses small tungsten-based cooling finger modules. The divertor parts are connected by brazing. They are cooled by helium impinging jets. After the performance and functionality of design has been confirmed through numerous high heat flux (HFF) tests, the current R&D focuses on the manufacturing technology in order to arrive at a robust design and a mass-production of parts. In this paper, newly developed innovative technologies for manufacturing tungsten-based divertor modules (e.g. deep drawing, powder injection molding) as well as for joining the components of different materials shall be presented.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"43 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":"115281052","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
Design and analysis of a high temperature and pressure he supplying system 高温高压给水系统的设计与分析
2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052311
E. Lee, Dong Won Lee, Suk-Kwon Kim, J. Yoon, Seungyon Cho
{"title":"Design and analysis of a high temperature and pressure he supplying system","authors":"E. Lee, Dong Won Lee, Suk-Kwon Kim, J. Yoon, Seungyon Cho","doi":"10.1109/SOFE.2011.6052311","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052311","url":null,"abstract":"In order to examine design and manufacturing techniques of the Korean Helium Cooled Molten Lithium (HCML) Test Blanket Module (TBM) for International Thermonuclear Experimental Reactor (ITER), we constructed a scale downed high temperature and high pressure helium supplying system which was linked with KoHLT-2 (Korea Heat Load Test-2). The main components for the helium supplying system (such as a circulator, a pre-heater and a heat exchanger) were designed and manufactured base on analyses of commercial CFD code, ANSYS-CFX V11. A trial operation is scheduled up to the design pressure (9 MPa), temperature (500 °C) and helium mass flow rate (0.5 kg/s). In the near future, the system with heat load test facilities is utilized to test various mock-ups and to validate code with the test data.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"13 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":"116674413","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
A real-time tracking for optimal wave injection in overdense plasma heating experiments at 140 GHz in FTU FTU 140 GHz超密等离子体加热实验中最佳波注入的实时跟踪
2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052324
W. Bin, E. Alessi, A. Bruschi, C. Galperti, G. Granucci, G. Grossetti, A. Moro, S. Nowak
{"title":"A real-time tracking for optimal wave injection in overdense plasma heating experiments at 140 GHz in FTU","authors":"W. Bin, E. Alessi, A. Bruschi, C. Galperti, G. Granucci, G. Grossetti, A. Moro, S. Nowak","doi":"10.1109/SOFE.2011.6052324","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052324","url":null,"abstract":"Experiments on overdense plasma heating through the mode-coupling scheme known as “O-X-B Double Mode Conversion”, obtained launching a narrow beam of millimeter-waves at 140 GHz frequency and 400 kW power, are scheduled for the next experimental campaigns of the FTU tokamak. Such a scheme, not yet demonstrated at electron density higher than the critical one (2.4·1020m−3) for the 140 GHz ordinary mode, and consequently at such a high frequency, exploits the conversion of an ordinary polarized wave (O) into the extraordinary (X) one, followed by a subsequent conversion to Bernstein (B) waves, which are then absorbed by the plasma. In the specific case of FTU the overall efficiency of this scheme is mainly determined by the coupling efficiency between the O- and the X-wave, which can occur only for ordinary polarized radiation propagating in a very narrow angular range at the cutoff region.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"62 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":"115660723","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
Iter In-Vessel Coil design and R&D Iter容器内线圈的设计与研发
2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052219
M. Kalish, P. Heitzenroeder, A. Brooks, L. Bryant, J. Chrzanowski, E. Daly, R. Feder, J. Feng, M. Messineo, M. Gómez, C. Hause, T. Bohm, I. Griffiths, A. Lipski, M. Mardenfeld, M. Nakahira, C. Neumeyer, R. Pillsbury, M. Sawan, M. Schaffer, R. Simmons, P. Titus, I. Zatz, T. Meighan
{"title":"Iter In-Vessel Coil design and R&D","authors":"M. Kalish, P. Heitzenroeder, A. Brooks, L. Bryant, J. Chrzanowski, E. Daly, R. Feder, J. Feng, M. Messineo, M. Gómez, C. Hause, T. Bohm, I. Griffiths, A. Lipski, M. Mardenfeld, M. Nakahira, C. Neumeyer, R. Pillsbury, M. Sawan, M. Schaffer, R. Simmons, P. Titus, I. Zatz, T. Meighan","doi":"10.1109/SOFE.2011.6052219","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052219","url":null,"abstract":"ITER will incorporate In Vessel Coils (IVCs) as a method of stabilizing “Edge Localized Modes” (ELM) and providing “Vertical Stabilization” (VS). To meet the ELM and VS Coil requirements strong coupling with the plasma is required so that it is necessary for the coils to be installed in the vessel just behind the blanket shield modules. Due to this close proximity to the plasma the radiation and temperature environment is severe and conventional electrical insulation materials and processes cannot be used. The development of mineral insulated conductor technology has been required in the IVC design to deal with this high radiation and high temperature environment. While mineral insulated conductor technology is not new, building a large magnet with high current carrying capability and a conductor diameter larger than the mineral insulated conductor currently manufactured requires R&D and the extension of existing technologies. A 59mm Stainless Steel Jacketed Mineral Insulated Conductor (SSMIC) using MgO is being developed for this application. The IVC ELM and VS coils design includes both the development of the fabrication techniques for the SSMIC and the design and analysis of the ELM and VS Coil assemblies.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"5 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":"114825130","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: 27
A similarity study on absorption/desorption cycles using ZrCo-H2 for ITER hydrogen getter material 用ZrCo-H2作为ITER吸氢剂材料吸/解吸循环的相似性研究
2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052246
S. Yun, Y. Oh, Seungyon Cho, M. Chang, Hyun-goo Kang, K. Jung, K. Song, H. Chung, D. Koo, M. Glugla
{"title":"A similarity study on absorption/desorption cycles using ZrCo-H2 for ITER hydrogen getter material","authors":"S. Yun, Y. Oh, Seungyon Cho, M. Chang, Hyun-goo Kang, K. Jung, K. Song, H. Chung, D. Koo, M. Glugla","doi":"10.1109/SOFE.2011.6052246","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052246","url":null,"abstract":"Consecutive absorption/desorption cycles of the ZrCo-H2 system were studied to simulate the real ITER hydrogen getter system. ZrCo getter was used in this study instead of the depleted uranium (DU) getter material which was recently considered as the hydrogen getter in ITER. In a cyclic PCI measurement the high-pressure Sievert apparatus seems impractical to describe the equilibrium state of the ZrCo-H2 system in detail, especially for the desorption stage. This high-pressure Pressure-Composition Isotherm (PCI) apparatus, however, shows a cause-and-effect well, from the previous getter state to the following state in presenting hydriding/dehydriding performance. In case of the ZrCo-H2 system or in case of the DU-H2 system, having multiple getter bed battery, a similar affection by the previous getter status might be related and a similar aspect could be shown to should consider further in ITER design, for example a need for control logic, from PCI measurements using a high-pressure Sievert apparatus.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"1 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":"128416797","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
Structural design and analysis of an ECRH launcher for JET 喷射发动机ECRH发射装置的结构设计与分析
2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052319
P. Spah, A. Vaccaro, G. Aiello, G. Giruzzi, M. Lennholm, C. Sozzi, D. Strauss
{"title":"Structural design and analysis of an ECRH launcher for JET","authors":"P. Spah, A. Vaccaro, G. Aiello, G. Giruzzi, M. Lennholm, C. Sozzi, D. Strauss","doi":"10.1109/SOFE.2011.6052319","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052319","url":null,"abstract":"The future JET (Joint European Torus) program will be mainly focused on the consolidation of the physics basis of the main ITER scenarios. This gives a strong motivation for examining the feasibility of the construction and implementation of an ECRH (Electron Cyclotron Resonance Heating) system in JET for an intensive exploitation before the start of ITER. To advance this feasibility study towards the approval of the project, collaboration between the E4J (ECRH for JET) project team and the KIT (Karlsruhe Institute of Technology) design team of the ITER ECH Port Plug was decided. The aim of this collaboration was to raise the principal design requirements and to establish a rough design of the main components of an E4J system.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"1696 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":"129391486","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
42GHz 0.5MW ECRH system for Tokamaks SST-1 and Aditya 用于托卡马克SST-1和Aditya的42GHz 0.5MW ECRH系统
2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052321
B. Shukla, R. Goswami, R. Babu, J. Patel, P. Chattopadhyay, R. Srinivasan, H. Patel, P. Dhorajia
{"title":"42GHz 0.5MW ECRH system for Tokamaks SST-1 and Aditya","authors":"B. Shukla, R. Goswami, R. Babu, J. Patel, P. Chattopadhyay, R. Srinivasan, H. Patel, P. Dhorajia","doi":"10.1109/SOFE.2011.6052321","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052321","url":null,"abstract":"A 42GHz ECRH system would be used to carry out pre-ionization and start-up experiments on Tokamaks SST-1 and Aditya. The system would give reliable start-up in SST-1 Tokamak at 1.5T operating toroidal magnetic field. Fundamental O-mode would be launched from low field side of tokamak. The same system would also be used in Tokamak Aditya to carry out second harmonic ECRH assisted breakdown experiments at 0.75T operation. The Gyrotron capable to deliver 500kW power would be installed such that it will deliver power to both the tokamaks without dismantling any component. It will be achieved by using two waveguide switches in the transmission line. First switch will divert power either to dummy load for Gyrotron testing or to launch power in the tokamaks. The second switch will give the option to transmit power either to tokamak Aditya or SST1. Approximately 50-meter long transmission line will be used to transmit power from Gyrotron to each tokamak. The transmission line consists of a matching optic unit, DC break, mitre-bends, polarizer, 63.5mm ID circular corrugated waveguide and bellows. The total transmission loss in the line is less than 20%, in this case we can launch ∼ 400kW power to carry out reliable ECRH assisted breakdown experiments at fundamental and second harmonic.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"81 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":"129642046","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
The ITER earthing topology: Mesh-Common Bonding Network ITER接地拓扑:网格-共键网络
2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052208
D. Beltran, K. Armstrong, A. Charoy, J. Hourtoule, D. Beltran, J. Hourtoule, K. Armstrong, A. Charoy
{"title":"The ITER earthing topology: Mesh-Common Bonding Network","authors":"D. Beltran, K. Armstrong, A. Charoy, J. Hourtoule, D. Beltran, J. Hourtoule, K. Armstrong, A. Charoy","doi":"10.1109/SOFE.2011.6052208","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052208","url":null,"abstract":"Electromagnetic Compatibility (EMC) is a key issue in the functioning of the industrial and scientific installation. ITER is one the world's most challenging projects, where the best EMC practices are required to ensure the operation of the machine. This document describes the design of the ITER MESH-Common Bonding Network (MESH-CBN), which is based on the international standards IEC 61000-5-2, IEC 62305-1 to 4 and the French rules for nuclear facilities (RCC-E), and which should improve the signal to noise ratio in the diagnostics signals by up to 60 dB, compared with classical single point designs. An experiment to demonstrate the benefits of a MESH-CBN in the Tokamak Alcator C-Mod in Boston is also described.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"48 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":"124020689","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
Measurement of RF transmission mode conversion due to waveguide thermal deformation using 170GHz gyrotron 用170GHz回旋管测量波导热变形引起的射频传输模式转换
2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052328
Y. Oda, K. Kajiwara, K. Takahashi, K. Sakamoto
{"title":"Measurement of RF transmission mode conversion due to waveguide thermal deformation using 170GHz gyrotron","authors":"Y. Oda, K. Kajiwara, K. Takahashi, K. Sakamoto","doi":"10.1109/SOFE.2011.6052328","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052328","url":null,"abstract":"The mode conversion by thermal deformation of the transmission line (TL) for electron cyclotron heating and current drive (EC H&CD) system caused by high-power long-pulse operation was studied. Mode contents in 40m length TL test stand were measured and compared for before and after the 600 kW / 169 s long-pulse operation. The mode content indicated that HE11 mode decreased by 10 % and LP11 mode increased. The miter bend after the 12 m long horizontal straight section in TL was moved for 1.5 mm which deformed the short vertical waveguide section. The increased LP11 mode was converted from HE11 mode in the deformed waveguide. Although the TL kept high transmission efficiency under high-power long-range TL, mode conversion loss was significantly increased by thermal deformation of TL.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"53 9","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2011-06-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"120812263","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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