2011 IEEE/NPSS 24th Symposium on Fusion Engineering最新文献_第7页

High pressure gas injection for suppression of runaway electrons in disruptions 高压气体注入抑制破坏中的失控电子

2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052212

L. Zakharov, S. Putvinski, A. Kukushkin, R. Pitts, M. Sugihara, S. Maruyama, S. Konovalov, V. Lukash

引用次数: 1

ITER Central Solenoid support structure analysis ITER中央螺线管支撑结构分析

2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052298

K. Freudenberg, R. Myatt

{"title":"ITER Central Solenoid support structure analysis","authors":"K. Freudenberg, R. Myatt","doi":"10.1109/SOFE.2011.6052298","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052298","url":null,"abstract":"The ITER Central Solenoid (CS) is comprised of six independent coils held together by a pre-compression support structure. This structure must provide enough preload to maintain sufficient coil-to-coil contact and interface load throughout the current pulse. End of burn (EOB) represents one of the most extreme time-points during the reference scenario when the currents in the CS3 coils oppose those of CS1 & CS2. The CS structure is performance limited by the room temperature static yield requirements needed to support the roughly 180 MN preload to resist coil separation during operation. This preload is applied by inner and external tie plates along the length of the coil stack by mechanical fastening methods utilizing Superbolt® technology. The preloading structure satisfies the magnet structural design criteria of ITER and will be verified during mockup studies. The solenoid is supported from the bottom of the toroidal field (TF) coil casing in both the vertical radial directions. The upper support of the CS coil structure maintains radial registration with the TF coil in the event of vertical disruptions (VDE) loads and earthquakes. All of these structure systems are analyzed via a global finite element analysis (FEA). The model includes a complete sector of the TF coil and the CS coil/structure in one self-consistent analysis. The corresponding results and design descriptions are described in this report.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"41 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":"123382522","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: 8

An overview of Pilot Plant designs based on the advanced tokamak, spherical tokamak and stellarator 基于先进托卡马克、球形托卡马克和仿星器的中试装置设计综述

2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052269

T. Brown, L. Bromberg, A. Costley, R. Goldston, L. El-Guebaly, C. Kessel, G. Neilson, S. Malang, J. Menard, S. Prager, S. Scott, L. Waganer, M. Zarnstorff

{"title":"An overview of Pilot Plant designs based on the advanced tokamak, spherical tokamak and stellarator","authors":"T. Brown, L. Bromberg, A. Costley, R. Goldston, L. El-Guebaly, C. Kessel, G. Neilson, S. Malang, J. Menard, S. Prager, S. Scott, L. Waganer, M. Zarnstorff","doi":"10.1109/SOFE.2011.6052269","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052269","url":null,"abstract":"A fusion pilot plant study was initiated to evaluate the potential benefits of following the fission development path as an approach for the commercialization of fusion. In such an approach, a fusion pilot plant would bridge the development needs in moving from ITER to a first of a kind fusion power plant. The pilot plant mission would encompass the component test and fusion nuclear science missions yet produce net electricity. In the first phase of the study scoping designs were developed for three different magnetic configuration options: the advanced tokamak (AT), spherical tokamak (ST) and compact stellarator (CS). Critical component features have been added to the designs that impact the general arrangement and maintenance characteristics of each device. The requirements specified in defining the pilot plant challenge the machine configurations developed for each option. Developing multiple options with a consistent set of requirements enables a uniform comparison of configuration and component issues that drive each design. This paper will provide an engineering design overview of each option, address open issues and assess where further work is needed to meet the pilot plant objectives.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"70 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":"123037208","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 Materials Analysis patticle Probe (MAPP) diagnostic system in NSTX NSTX的材料分析颗粒探针(MAPP)诊断系统

2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052303

B. Heim, S. Gonderman, C. Taylor, J. Allain, Z. Yang, M. González, E. Collins, C. Skinner, B. Ellis, W. Blanchard, L. Roquemore, H. Kugel, R. Martín

{"title":"The Materials Analysis patticle Probe (MAPP) diagnostic system in NSTX","authors":"B. Heim, S. Gonderman, C. Taylor, J. Allain, Z. Yang, M. González, E. Collins, C. Skinner, B. Ellis, W. Blanchard, L. Roquemore, H. Kugel, R. Martín","doi":"10.1109/SOFE.2011.6052303","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052303","url":null,"abstract":"Lithium conditioning of plasma-facing surfaces (PFS) has been implemented in NSTX leading to improvements in plasma performance such as reduced D recycling and a reduction in edge localized modes (ELMS). Analysis of post-mortem tiles and offline experiments has identified interactions between Li-O-D and Li-C-D as chemical channels for deuterium retention in ATJ graphite. MAPP is the first in-vacuo surface analysis diagnostic directly integrated into a tokamak and capable of shot-to-shot chemical surface analysis of plasma material interactions (PMI). X-ray photoelectron spectroscopy (XPS) and low energy ion surface spectroscopy (LEISS) can show the chemical functionalities between D and lithiated graphite at both the near surface (5–10 nm) and top surface layer (0.3–0.6 nm) for XPS and LEISS respectively. MAPP will correlate plasma facing component (PFC) surface chemistry with plasma performance to lead the way to improved understanding of plasma-surface interactions and their effect on global plasma performance. Remote operation and data acquisition, integrated into NSTX diagnostic and interlocks, make MAPP an advanced PMI diagnostic with stringent engineering constraints.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"63 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":"131542809","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

5kHz modulation of 170 GHz gyrotron with anode-cathode short-circuited switch 带阳极-阴极短路开关的170 GHz回旋管5kHz调制

2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052214

K. Kajiwara, Kazuo Hayashi, Y. Oda, Koji Takahashi, A. Kasugai, K. Sakamoto

引用次数: 7

Advanced concepts for fusion power supplies 核聚变电源的先进概念

2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052200

X. Yao, Y. Huang, F. Guo, J. Wang

{"title":"Advanced concepts for fusion power supplies","authors":"X. Yao, Y. Huang, F. Guo, J. Wang","doi":"10.1109/SOFE.2011.6052200","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052200","url":null,"abstract":"Nuclear fusion reactors, such as the Tokamak in the International Thermonuclear Experimental Reactor (ITER) project, usually involve extremely sophisticated high voltage power supply systems, which provide exciting research challenges. In the short term, the major challenges in power supplies of the ITER and other fusion reactors include 1) fast current control of Vertical Stabilization (VS) coils; and 2) dynamic compensation of reactive power and harmonics. In the long term, the power supply systems in fusion reactors provide opportunities for optimizations at both component and system levels. In this paper, modular multilevel converters (M2LC) are adopted to tackle the short term challenges. Circuit structures, PWM methods, and fault tolerant operation strategies are presented. The configuration and control strategies of M2LC in VS coils are fully studied and verified with real time simulations. Compared with existing circuit solutions in fusion reactors, the M2LC based circuits will have better dynamic response, higher reliability, smaller footprint, and reduced weight. As an outlook to the long term developments of the fusion power supplies, comprehensive real time simulations are also discussed at the end of the paper.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"17 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":"114522761","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

SST-1status & plans sst -1状态和计划

2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052353

S. Pradhan, A. Sharma, V. Tanna, Z. Khan, U. Prasad, D. Raval, F. Khan, N. Gupta, J. Tank, M. Gupta, P. Santra, P. Biswas, H. Masand, D. Sharma, A. Srivastava, H. Patel

{"title":"SST-1status & plans","authors":"S. Pradhan, A. Sharma, V. Tanna, Z. Khan, U. Prasad, D. Raval, F. Khan, N. Gupta, J. Tank, M. Gupta, P. Santra, P. Biswas, H. Masand, D. Sharma, A. Srivastava, H. Patel","doi":"10.1109/SOFE.2011.6052353","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052353","url":null,"abstract":"Steady State Tokamak (SST-1) is currently being refurbished in a mission mode at the Institute for Plasma Research with an ultimate objective of producing the first plasma in early 2012. Since Jan 2009, under the SST-1 Mission mandate, a broad spectrum of refurbishment activities have been initiated and pursued on several subsystems of SST-1. Developing sub nano-ohm leak tight joints in the magnet winding packs, developing single phased LN2 cooled thermal shields, developing supercritical helium cooled 5 K thermal shields for magnet cases, insurance of thermal and electrical isolations between various sub-systems of SST-1, testing of each of the SST-1 Toroidal Field (TF) magnets in cold with nominal currents, testing each of the modules and octants of SST-1 machine shell in representative experimentally simulated scenarios, augmentation and reliability establishment of the SST-1 vacuum vessel baking system, time synchronizations amongst various heterogeneous subsystems of SST-1, large data storage scenarios, integrated engineering testing of the first phase of the plasma diagnostics etc are some of the major refurbishment activities. Presently, the SST-1 device integration is in full swing. The cold test of the assembled SST-1 TF and PF magnets are due to begin from Dec 2011. Following the successful testing of the SST-1 superconducting magnet system and engineering validations of the machine shell, the first plasmas will be attempted in SST-1. The first plasma will be ∼ 100 kA limiter assisted with the available volt-sec and could possibly be assisted by ECCD/LHCD.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"45 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":"115853990","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

Cryogenic viscous compressor development and modeling for the ITER vacuum system ITER真空系统低温粘性压缩机的研制与建模

2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052261

L. Baylor, S. Meitner, C. Barbier, S. Combs, R. Duckworth, T. G. Edgemon, D. Fehling, D. Rasmussen, M. Hechler, R. Kersevan, M. Dremel, R. Pearce, J. Boisson

引用次数: 8

New developments for real time plasma control system on HL-2A HL-2A实时等离子体控制系统的新进展

2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052254

F. Xia, Li Zhao, Liao-yuan Chen

引用次数: 3

Upgrade of converter unit of EAST poloidal field power supply EAST极向场电源转换单元的改造

2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052228

G. Gao, L. Huang, L. Tang, L.S. Wang, S. He, P. Fu

引用次数: 9