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

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Nuclear analysis in support of the design of ITER blanket modules 支持ITER包层模块设计的核分析
2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052350
M. Sawan
{"title":"Nuclear analysis in support of the design of ITER blanket modules","authors":"M. Sawan","doi":"10.1109/SOFE.2011.6052350","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052350","url":null,"abstract":"Detailed profiles of nuclear heating and radiation damage parameters were determined in ITER blanket modules at different poloidal locations. The results indicate that the nuclear parameters are sensitive to the configuration and material composition with enhanced steel heating and helium production in regions with large water content.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"37 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":"126799384","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
Laser welding of plasma facing units for ITER divertor Dome manufacturing ITER导流罩制造等离子体端面单元的激光焊接
2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052257
S. Mazaev, T. Gurieva, A. Lapin, A. Makhankov, V. Mirgorodsky, S. Natochev, O. Nomokonova, I. Vlasov, A. Ignatov
{"title":"Laser welding of plasma facing units for ITER divertor Dome manufacturing","authors":"S. Mazaev, T. Gurieva, A. Lapin, A. Makhankov, V. Mirgorodsky, S. Natochev, O. Nomokonova, I. Vlasov, A. Ignatov","doi":"10.1109/SOFE.2011.6052257","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052257","url":null,"abstract":"The ITER divertor is a modular structure consisting of 54 cassettes. Each cassette consists of the cassette body, inner and outer vertical targets and Dome. The Russian Federation is responsible for manufacturing and delivery of 60 Domes for ITER. Each Dome consists of the steel support structure with 34 plasma-facing units of Umbrella, Inner Particle Reflector Plate and Outer Particle Reflector Plate (OPRP). The steel support structure includes three manifolds. Each plasma-facing unit part from 316L(N)-IG steel is supposed to be welded by laser beam welding.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"338 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":"123126950","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: 6
Overview of ITER magnet system and European contribution ITER磁体系统概述及欧洲贡献
2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052218
C. Sborchia, E. Barbero Soto, R. Batista, B. Bellesia, A. Bonito Oliva, E. Boter Rebollo, T. Boutboul, E. Bratu, J. Caballero, M. Cornelis, J. Fanthome, R. Harrison, M. Losasso, A. Portone, H. Rajainmaki, P. Readman, P. Valente
{"title":"Overview of ITER magnet system and European contribution","authors":"C. Sborchia, E. Barbero Soto, R. Batista, B. Bellesia, A. Bonito Oliva, E. Boter Rebollo, T. Boutboul, E. Bratu, J. Caballero, M. Cornelis, J. Fanthome, R. Harrison, M. Losasso, A. Portone, H. Rajainmaki, P. Readman, P. Valente","doi":"10.1109/SOFE.2011.6052218","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052218","url":null,"abstract":"The superconducting magnet system of ITER consists of four main sub-systems: Toroidal Field (TF) coils, Central Solenoid (CS) coils; Poloidal Field (PF) coils; and Correction Coils (CC). Like many other ITER systems, the magnet components are supplied in-kind by six Domestic Agencies (DAs). The technical specifications, manufacturing processes and procedures required to fabricate these components are particularly challenging. The management structure and organization to realize this procurement within the tight ITER construction schedule is very complex.","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":"127917637","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: 13
Development of & integration of the IC H&CD system configuration in the ITER Tokamak complex and auxiliary buildings ITER托卡马克综合体和辅助建筑中IC H&CD系统配置的开发与集成
2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052322
D. Rathi, B. Beaumont, B. Arambhadiya, B. Beckett, B. Bruyere, T. Gassmann, F. Kazarian, P. Lamalle, E. Manon, T. Alonzo, R. Goulding, R. Moon, D. Rasmussen, D. Swain, U. Baruah, R. Kumar, A. Mukherjee, N. Singh, R. Singh, R. Trivedi, G. Agarici, L. Meunier, M. Mills, R. Sartori, J. Bernard, F. Durodié, M. Nightingale, M. Shannon, D. Lockley
{"title":"Development of & integration of the IC H&CD system configuration in the ITER Tokamak complex and auxiliary buildings","authors":"D. Rathi, B. Beaumont, B. Arambhadiya, B. Beckett, B. Bruyere, T. Gassmann, F. Kazarian, P. Lamalle, E. Manon, T. Alonzo, R. Goulding, R. Moon, D. Rasmussen, D. Swain, U. Baruah, R. Kumar, A. Mukherjee, N. Singh, R. Singh, R. Trivedi, G. Agarici, L. Meunier, M. Mills, R. Sartori, J. Bernard, F. Durodié, M. Nightingale, M. Shannon, D. Lockley","doi":"10.1109/SOFE.2011.6052322","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052322","url":null,"abstract":"The Ion Cyclotron Heating and Current Drive (IC H & CD) system for ITER will provide Radio frequency (RF) heating and current drive to the ITER plasma. This system is designed to provide 20 MW into the plasma using frequencies in the range of 40 MHz to 55 MHz, which could be upgraded to 40 MW in future. This paper presents the recent development of the IC H&CD system configuration in the ITER Tokamak complex & auxiliary buildings with developed interfaces.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"9 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":"132418319","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
ARIES systems code development, visualization and application ARIES系统的代码开发、可视化和应用
2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052294
L. Carlson, M. Tillack, F. Najmabadi, C. Kessel
{"title":"ARIES systems code development, visualization and application","authors":"L. Carlson, M. Tillack, F. Najmabadi, C. Kessel","doi":"10.1109/SOFE.2011.6052294","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052294","url":null,"abstract":"The ARIES research program has utilized its comprehensive ARIES systems code (ASC) and a new graphical user interface for visualizing the parameter space as important tools in its analysis of fusion power plant designs. Recently, the ASC has undergone modifications to accommodate different divertor designs, each having unique pumping powers, helium and liquid-metal pumps thermal heat recovery, and the latest material, fabrication, and costing algorithms. The modifications and changes made to the code have been documented and verified by members of the ARIES team to ensure accuracy of implementation and self-consistency of design. The code has also been modified to display a wider range of inputs/outputs, formulas, and algorithms for a greater degree of transparency and verification.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"123 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":"132828509","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
Advances on the high speed ignitor Pellet Injector (IPI) 高速点火器颗粒喷射器(IPI)研究进展
2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052237
A. Frattolillo, F. Bombarda, S. Migliori, S. Podda, M. Capobianchi, S. Combs, C. Foust, S. Meitner, D. Fehling, J. Mc Gill, L. Baylor, S. Milora, B. Coppi, G. Roveta
{"title":"Advances on the high speed ignitor Pellet Injector (IPI)","authors":"A. Frattolillo, F. Bombarda, S. Migliori, S. Podda, M. Capobianchi, S. Combs, C. Foust, S. Meitner, D. Fehling, J. Mc Gill, L. Baylor, S. Milora, B. Coppi, G. Roveta","doi":"10.1109/SOFE.2011.6052237","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052237","url":null,"abstract":"The control of the density profile during the initial plasma current rise is a critical issue to optimize ohmic and fusion heating rates of Ignitor plasmas. Simulations performed with the NGS ablation model, for the reference ignition plasma parameters (n<inf>e0</inf> ≅ n<inf>i0</inf> ≅ 10<inf>21</inf> m<inf>−3</inf>, T<inf>e0</inf> ≅ T<inf>i0</inf> ≅ 11 keV), indicate that deuterium pellets of a few mm (≤ 4 mm) in size injected at 3–4 km/s from the low field side should ensure adequate deep fuelling.","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":"130445392","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
Stress multipliers for the NSTX upgrade digital coil protection system 应力倍增器用于NSTX升级数字线圈保护系统
2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052287
P. Titus, R. Woolley, R. Hatcher
{"title":"Stress multipliers for the NSTX upgrade digital coil protection system","authors":"P. Titus, R. Woolley, R. Hatcher","doi":"10.1109/SOFE.2011.6052287","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052287","url":null,"abstract":"Conceptual design of the upgrade to NSTX, explored designs sized to accept the worst loads that power supplies could produce. This produced excessive structures that would have been difficult to install and were much more costly than needed to meet the scenarios required for the upgrade mission. Instead, the project decided to rely on a digital coil protection system (DCPS). Initial sizing was then based on the 96 scenarios in the project design point with some headroom to accommodate operational flexibility and uncertainty. This has allowed coil support concepts that minimize alterations to the existing hardware. The digital coil protection system theory, hardware and software are described in another paper at this conference. The intention of this paper is to describe the generation of stress multipliers, and algorithms that are used to characterize the stresses at key areas in the tokamak, as a function of either loads calculated by the influence coefficients computed in the DCPS software, or directly from the coil currents.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"20 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":"125266389","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: 6
ITER Radiological and Environmental Monitoring Systems conceptual design elements ITER辐射与环境监测系统概念设计要素
2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052235
L. Perna, S. Molinaro, M. Berruyer
{"title":"ITER Radiological and Environmental Monitoring Systems conceptual design elements","authors":"L. Perna, S. Molinaro, M. Berruyer","doi":"10.1109/SOFE.2011.6052235","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052235","url":null,"abstract":"A state of the art Radiological and Environmental Monitoring Systems (REMS) is being developed by the ITER Organization, with the engineering support of Fusion for Energy. The primary functions of REMS are to provide health and radiological monitoring for workers as well as area environmental monitoring for the public and thus to assist in the protection against ionizing radiation during ITER operations, including maintenances, and decommissioning. The Radiologically-Controlled Facilities at ITER, to be monitored by REMS are the Tokamak Building, the Tritium Plant Building, the Hot Cell Facility, the Radwaste Facility and the Personnel Access Control Building. Starting from the safety functions assigned to the systems and the requirements imposed by French legislation, embedded in the ITER Preliminary Safety Report, this paper describes the identified REM systems, sub-systems, architectures, safety classification and equipments, and provides the actual status of its design.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"72 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":"127139139","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
Magnetic diffusion models for FAST toroidal magnet coils FAST环形磁线圈的磁扩散模型
2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052275
V. Cocilovo
{"title":"Magnetic diffusion models for FAST toroidal magnet coils","authors":"V. Cocilovo","doi":"10.1109/SOFE.2011.6052275","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052275","url":null,"abstract":"FAST is a project of a compact high-field tokamak (up to 8.5 T) with copper coils ( either for toroidal and poloidal fields) operated at cryogenic temperatures (30 °K) to get a higher electrical conductivity of the copper and to permit an adiabatic duty cycle, i.e. the coils cooling is carried out between two consecutive pulses, to minimize the coils size.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"22 8 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":"125782495","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
Multi-secondary transformer: A modeling technique for simulation 多二次变压器:一种仿真建模技术
2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052231
A. Patel, N. Singh, B. Raval, A. Roy, A. Thakar, D. Parmar, H. Dhola, R. Dave, S. Gajjar, Vikrant Gupta, U. Baruah, V. Tripathi, L. Gupta, P. Patel
{"title":"Multi-secondary transformer: A modeling technique for simulation","authors":"A. Patel, N. Singh, B. Raval, A. Roy, A. Thakar, D. Parmar, H. Dhola, R. Dave, S. Gajjar, Vikrant Gupta, U. Baruah, V. Tripathi, L. Gupta, P. Patel","doi":"10.1109/SOFE.2011.6052231","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052231","url":null,"abstract":"Pulse Step Modulation based High voltage power supply has played significant role in fusion research. Multi-Secondary transformers are invariably used for generation of tens of kV range outputs with fast (µS order) transient response. In this scheme, large numbers of isolated voltage sources are connected in series to generate the output. Isolated voltage sources can be achieved by large number of separate transformers or by single unit of multi-secondary transformer. Naturally, a transformer having numbers of secondary windings (∼40) on single core is the preferred solution due to its space and cost consideration. For design and simulation analysis of such a power supply, the model of a multi-secondary transformer poses special problem to any circuit analysis software. While many simulation softwares provide transformer models with limited number (3–6) of secondary windings, they still fail to predict the actual observed results from a manufactured unit. This paper discusses the difficulties in modelling, step by step with representative schemes of multi-secondary transformer, advantages/disadvantages of each scheme with simulation results. Finally, a model using flux coupled cores as basic building block is proposed, this model is able to simulate actual transformers very close to its observed parameters in test and actual usage.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"100 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":"126055068","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
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