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

筛选
英文 中文
R & D of polyimide insulated JET ELM control coils for operation at 350 C 研发在350℃下运行的聚酰亚胺绝缘JET ELM控制线圈
2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052284
I. Zatz, G. H. Neilson, S. Jurczynski, M. Mardenfeld, C. Lowry
{"title":"R & D of polyimide insulated JET ELM control coils for operation at 350 C","authors":"I. Zatz, G. H. Neilson, S. Jurczynski, M. Mardenfeld, C. Lowry","doi":"10.1109/SOFE.2011.6052284","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052284","url":null,"abstract":"A study has confirmed the feasibility of designing, fabricating and installing resonant magnetic field perturbation (RMP) coils in JET with the objective of controlling edge localized modes (ELM). These coils present several engineering challenges. Conditions in JET necessitate the installation of these coils via remote handling, which will impose weight, dimensional and logistical limitations. And while the encased coils are designed to be conventionally wound and bonded, they will not have the usual benefit of active cooling. Accordingly, coil temperatures are expected to reach 350C during bakeout as well as during plasma operations from resistive heating. These elevated temperatures are beyond the safe operating limits of conventional OFHC copper and the epoxies that bond and insulate the turns of typical coils. This has necessitated the use of an alternative copper alloy conductor C18150 (CuCrZr). More importantly, an alternative to epoxy had to be found. An R&D program was initiated to find the best available insulating and bonding material. The search included polyimides and ceramic polymers. Ultimately, these ELM coils must be able to withstand the elevated thermal conditions as well as the structural stresses resulting from electromagnetic loads, which include eddy current and halo current effects. Not only do these loads affect the performance of the coils and cases, but also impact the design of joints, leads, jumpers, and the mounting of the coils to the interior of the vacuum vessel wall. In order to qualify the proposed insulating and bonding materials, prototypical coil samples were built to the design specifications of the proposed JET ELM coils. These samples were impregnated with polyimide then cured. This paper will detail the R&D program, including the results of testing to determine mechanical properties of the polyimide bonded coil samples.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"7 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":"127055695","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
Advances in the FAST program FAST项目的进展
2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052312
A. Cucchiaro, G. Brolatti, G. Calabrò, V. Cocilovo, P. Frosi, F. Crescenzi, F. Crisanti, G. Maddaluno, V. Pericoli-Ridolfini, A. Pizzuto, C. Rita, G. Ramogida, S. Roccella, P. Rossi
{"title":"Advances in the FAST program","authors":"A. Cucchiaro, G. Brolatti, G. Calabrò, V. Cocilovo, P. Frosi, F. Crescenzi, F. Crisanti, G. Maddaluno, V. Pericoli-Ridolfini, A. Pizzuto, C. Rita, G. Ramogida, S. Roccella, P. Rossi","doi":"10.1109/SOFE.2011.6052312","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052312","url":null,"abstract":"FAST (Fusion Advanced Studies Torus) is a proposal for a Satellite Facility which can contribute the rapid exploitation of ITER and prepare ITER and DEMO regimes of operation, as well as exploiting innovative DEMO technology. FAST operates with high performance H-Mode (BT up to 8.5 T; IP up to 8 MA) as well as Advanced Tokamak operation (IP=3 MA), and full non inductive current scenario (IP=2 MA) [1]. The project is based on a dominant 30 MW of ICRH, 6 MW of LH and 4 MW of ECRH.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"26 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":"127913478","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 disruption mitigation requirements and development of gas cartridge concept ITER中断缓解要求和气体筒概念的发展
2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052232
S. Maruyama, S. Putvinski, M. Sugihara, G. Kiss, R. Marrs, B. Macdonald, P. Edwards
{"title":"ITER disruption mitigation requirements and development of gas cartridge concept","authors":"S. Maruyama, S. Putvinski, M. Sugihara, G. Kiss, R. Marrs, B. Macdonald, P. Edwards","doi":"10.1109/SOFE.2011.6052232","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052232","url":null,"abstract":"ITER is designed to withstand a certain number of full scale plasma disruptions. Each disruption event induces excessive thermal loads, electromagnetic (EM) loads and runaway electrons onto the vacuum vessel and in-vessel components; the consequences of unmitigated events are extremely serious in terms of component lifetimes. This paper describes the preliminary requirements for the disruption mitigation system (DMS), possible approaches to mitigate the disruption in ITER, the schemes compatible with ITER operation and an on-going pre-conceptual study on gas cartridge DMS, which is one of the massive gas injection DMS schemes.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"4 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":"121026145","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
Temporal and spatial PFC temperature profiles in KSTAR 2010 KSTAR 2010的PFC温度时空分布
2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052256
E. Bang, K.M. Kim, H. Kim, H. Kim, K.S. Lee, S. Hong, Y. Jeon, J. Bak, W. Kim, H. Yang, Y. Oh
{"title":"Temporal and spatial PFC temperature profiles in KSTAR 2010","authors":"E. Bang, K.M. Kim, H. Kim, H. Kim, K.S. Lee, S. Hong, Y. Jeon, J. Bak, W. Kim, H. Yang, Y. Oh","doi":"10.1109/SOFE.2011.6052256","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052256","url":null,"abstract":"In- and outboard Plasma Facing Components (PFCs) of KSTAR (Korea Superconducting Tokamak Advanced Reasearch) have been fully installed in 2010 for D shaped diverted plasmas. Before the start of plasma operation, the PFCs were baked up to 200 °C by hot nitrogen gas circulation system to remove impurities including water. The surface temperature of the PFC tiles was monitored by 200 thermo-couple sensors during the plasma operation (plasma shot or Glow Discharge Cleaning(GDC)), and the temporal and spatial (poloidal) temperature profiles are obtained. Depending on the heat flux on each tile, the surface temperature shows time-dependency. After 1-hour morning He GDC, the temperature of the PFCs at inboard side has reached at 40 °C. After an H-mode shot, the temperature of divertor tiles around the striking points was substantially increased. The time-averaged total heat flux after an specific H-mode in 2010 was estimated to be approximately 10kW/m2.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"99 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":"122537009","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
The analysis of the electromagnetic loads on selected ITER blanket shield modules due to induced eddy and halo currents ITER包层屏蔽模块在感应涡流和晕流作用下的电磁载荷分析
2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052206
J. Kotulski, R. Coats, M. Ulrickson
{"title":"The analysis of the electromagnetic loads on selected ITER blanket shield modules due to induced eddy and halo currents","authors":"J. Kotulski, R. Coats, M. Ulrickson","doi":"10.1109/SOFE.2011.6052206","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052206","url":null,"abstract":"The prediction of electromagnetic loads on the ITER blanket modules during a plasma disruption is considered for two different blanket modules and different disruption events.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"14 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":"134265722","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
High temperature plasma facing components designs for biomass hybrid reactor: GNOME 生物质混合反应器的高温等离子体面组件设计:GNOME
2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052203
K. Ibano, S. Konishi, Y. Yamamoto
{"title":"High temperature plasma facing components designs for biomass hybrid reactor: GNOME","authors":"K. Ibano, S. Konishi, Y. Yamamoto","doi":"10.1109/SOFE.2011.6052203","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052203","url":null,"abstract":"Neutronics analysis for a tokamak reactor GNOME was studied by a three dimensional Monte Calro simulation code; MCNP-5. Distribution of nuclear heat was obtained from the calculated and applied into in-board cooling duct designs for the GNOME reactor. The pressure drop at the duct and corresponding pumping power were evaluated to survey the operational windows of the tokamak with SiC insulated He/PbLi dual coolants blankets. Besides, the pressure drop at the SiC structure PbLi cooled divertor was also evaluated in order to confirm the feasibility of the PbLi cooled divertor.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"97 3 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":"115701030","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
Dynamic study of a helium refrigerator for tokamak 托卡马克氦制冷机的动力学研究
2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052272
L. Qiu, M. Zhuang, L. Hu, J. Mao, X. Hao
{"title":"Dynamic study of a helium refrigerator for tokamak","authors":"L. Qiu, M. Zhuang, L. Hu, J. Mao, X. Hao","doi":"10.1109/SOFE.2011.6052272","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052272","url":null,"abstract":"Dynamic heat loads of the helium cryoplant of tokamak device due to operation of the magnet system, increase with the progress of the physics experiments, and may cause instability to the helium refrigerator. This paper presents the study of dynamic performance and behavior of EAST tokamak refrigerator from experiments and simulations. The dynamic effects on components depend on the variations of the heat loads and the ways to smooth and control of the system. This study aims to evaluate the stability of a helium refrigerator during high-current and long-pulsed plasma operation, discuss good methods to smooth the dynamic heat loads and to control the refrigerator. It will help to propose better operational way of the total helium cryogenic system in future.","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":"115708019","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
ITER Coil Power Supply and Distribution System ITER线圈供配电系统
2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052201
J. Tao, I. Benfatto, J. Goff, A. Mankani, F. Milani, I. Song, H. Tan, J. Thomsen
{"title":"ITER Coil Power Supply and Distribution System","authors":"J. Tao, I. Benfatto, J. Goff, A. Mankani, F. Milani, I. Song, H. Tan, J. Thomsen","doi":"10.1109/SOFE.2011.6052201","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052201","url":null,"abstract":"The ITER Coil Power Supply and Distribution System (CPSDS) will be installed to receive power from the French 400 kV transmission grid and to provide controlled DC power to the superconducting tokamak magnets for plasma operation.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"1245 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":"114165505","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: 94
A small rectangular Edge Localized Mode control coil design able to withstand a 400°C environment 一个小矩形边缘局部化模式控制线圈设计能够承受400°C的环境
2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052292
M. Viola, F. Dahlgren, P. Heitzenroeder, T. Meighan, P. Titus, P. Anderson, A. Kellman
{"title":"A small rectangular Edge Localized Mode control coil design able to withstand a 400°C environment","authors":"M. Viola, F. Dahlgren, P. Heitzenroeder, T. Meighan, P. Titus, P. Anderson, A. Kellman","doi":"10.1109/SOFE.2011.6052292","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052292","url":null,"abstract":"Recently, an Edge Localized Mode (ELM) control coil was developed for use on the DIII-D tokamak. The coil design represented a significant challenge due primarily to the requirement for the coil insulation to withstand bakeout temperatures of 400°C for extended periods. This requirement ruled out most common organic insulating systems and necessitated a significant prototyping and development effort, leading to the selection of an advanced high temperature glass/polyimide resin system. The development included developing a heating mechanism that provided the discrete temperature ramp cycles and cure cycles required by this exotic resin. To complicate matters, the resin had a limited shelf life. Additionally the coil was small and rectangular in shape with rather small corner radii. This created a corner buildup that was not previously encountered and made dimensional control difficult. Another unique design requirement was the need to apply a sufficient internal pre-load to the wound and cured coil to insure there will be no relative motion between the coil and the Inconel case due to Lorentz forces from the 4 Tesla toroidal field on the vessel center post. This led to development of very unique leaf springs and a significant research and development effort coupled with an equally arduous finite element analysis effort. A satisfactory prototype was produced. This paper will focus primarily on the manufacturing challenges and discuss the prototyping effort.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"90 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":"114216749","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
Korean R&D on the converter controller for ITER AC/DC converters 韩国研发ITER AC/DC变换器的变换器控制器
2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052337
J. Suh, J. S. Oh, J. Choi, E. Song, G. S. Lee, K. Eom, J. Goff, J. Tao, P. Fu
{"title":"Korean R&D on the converter controller for ITER AC/DC converters","authors":"J. Suh, J. S. Oh, J. Choi, E. Song, G. S. Lee, K. Eom, J. Goff, J. Tao, P. Fu","doi":"10.1109/SOFE.2011.6052337","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052337","url":null,"abstract":"The ITER coil power supplies provide controlled DC current to charge and stabilize the current in a toroidal field (TF) coil, and to establish and control the currents in a central solenoid (CS) module, poloidal field (PF) coils, and correction coils (CC) for the position and shape control of plasma. They consist of different types of AC/DC converters to meet the various operating requirements. The controller design for ITER AC/DC converters is based on the plant control design handbook as an ITER design guideline. There are basically three networks such as CODAC (COntrol, Data Access and Communication) network, central interlock network, central safety network for ITER instrumentation and control. Korean Domestic Agency has been being performing converter R&D to establish the technical basis for the procurement package of ITER AC/DC converter. The R&D on converter controller is under progress to implement a real time control and monitoring, interlock for equipment protection and emergency shutdown, personnel safety. The dynamic control algorithm to realize a fast response with high fidelity, high speed real time control, communication hardware and configuration are key issues. ITER converters are simulated by small-scaled test bed for AC/DC converters controlled by a CODAC simulator using a cPCI (compactPCI), a fast controller using a cPCI, a Plant System Host and a Siemens S7-300 PLC. The small-scaled test bed has an embedded controller based on digital signal processing and field-programmable gate array technology. This paper shows the detail description of the test bed and test results of the real time control and monitoring, sequential control, circulating current mode, etc.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"29 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":"115478025","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: 7
0
×
引用
GB/T 7714-2015
复制
MLA
复制
APA
复制
导出至
BibTeX EndNote RefMan NoteFirst NoteExpress
×
提示
您的信息不完整,为了账户安全,请先补充。
现在去补充
×
提示
您因"违规操作"
具体请查看互助需知
我知道了
×
提示
确定
请完成安全验证×
相关产品
×
本文献相关产品
联系我们:info@booksci.cn Book学术提供免费学术资源搜索服务,方便国内外学者检索中英文文献。致力于提供最便捷和优质的服务体验。 Copyright © 2023 布克学术 All rights reserved.
京ICP备2023020795号-1
ghs 京公网安备 11010802042870号
Book学术文献互助
Book学术文献互助群
群 号:604180095
Book学术官方微信