2009 23rd IEEE/NPSS Symposium on Fusion Engineering最新文献_第3页

Design and commissioning of the MAST neutral beam power supplies for the long pulse beam upgrade 用于长脉冲波束升级的MAST中性波束电源的设计和调试

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226416

P. Stevenson, R. Baldwin, V. Dunkley, A. Vadgama, S. Warder

引用次数: 3

Calculated beam profiles for the DIII-D off-axis and long pulse neutral beam upgrade 计算了DIII-D离轴和长脉冲中性光束升级的光束轮廓

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226419

H. Chiu, R. Hong, J. Scoville

{"title":"Calculated beam profiles for the DIII-D off-axis and long pulse neutral beam upgrade","authors":"H. Chiu, R. Hong, J. Scoville","doi":"10.1109/FUSION.2009.5226419","DOIUrl":"https://doi.org/10.1109/FUSION.2009.5226419","url":null,"abstract":"An analysis of the propagation of a neutral beam along the axis of injection was performed. An analytic solution was found using a population of Gaussian point sources uniformly distributed on a surface in Cartesian coordinates normal to the direction of beam travel. The solution was extended to examine the effects of multiple source surfaces, incorporating the canting of the source surfaces that enables focusing the neutral beam. The model was then used to analyze the current DIII-D neutral beam ion sources (with an initial beam size of 12 × 48 cm) to obtain the beam profiles and intensities at locations downstream of the source plane. The calculated intensity profiles along the axis of beam travel lead to estimates of the scrape-off beam power loss to the beamline internal components. These results were compared to previous water-flow-calorimetry measurements of beam power depositions on the beamline internal components to validate the model. The model was then employed to calculate the beam profiles and beam intensities for the smaller aperture ion sources (12 × 43 cm) planned for use on the off-axis beamline. The calculated data are used in the mechanical and thermal analyses for the design of the internal components for the future off-axis beamline. The off-axis beamline will be capable of operating at 80 keV beam energy for pulse lengths up to 10 seconds. We present a description of the analysis methodology, the calculated and measured power deposition results, and a discussion of the implications and limitations of the analysis.","PeriodicalId":236460,"journal":{"name":"2009 23rd IEEE/NPSS Symposium on Fusion Engineering","volume":"13 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2009-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"125573123","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

Experimental analysis of MHD pressure drop in a HCLL blanket mock-up HCLL毛毯模型中MHD压降的实验分析

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226526

C. Mistrangelo, L. Buhler

引用次数: 2

IRES: a code evaluating the beamlet beamlet interaction for multi-aperture electrostatic accelerators 评价多孔径静电加速器的束流相互作用的代码

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226536

N. Pilan, G. Serianni, V. Antoni

引用次数: 1

National spherical torus experiment (NSTX) Center Stack Upgrade 国家球面环面实验(NSTX)中心栈升级

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226399

C. Neumeyer, S. Avasarala, J. Chrzanowski, L. Dudek, H. Fan, R. Hatcher, P. Heitzenroeder, J. Menard, M. Ono, S. Ramakrishnan, P. Titus, R. Woolley, H. Zhan

引用次数: 13

Electromagnetic analysis of forces and torques on the ITER shield modules due to plasma disruption 等离子体破坏对ITER屏蔽模块的力和扭矩的电磁分析

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226486

J. Kotulski, R. Coats, M. Pasik, M. Ulrickson

引用次数: 0

Utilizing zfs for the storage of acquired data 利用zfs存储获取的数据

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226462

C. Pugh, P. Henderson, K. Silber, T. Carroll, K. Ying

引用次数: 1

Benchmarking FENDL-2.1 with impact of ENDF/B-VII.0 release on nuclear heating and damage 基准测试FENDL-2.1与ENDF/B-VII的影响。0释放对核加热和损坏

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226370

M. Sawan

引用次数: 0

Structural design of the iter ec upper launcher iter上部发射装置的结构设计

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226495

P. Spaeh, R. Heidinger, K. Kleefeldt, A. Meier, T. Scherer, A. Serikov, D. Strauss, A. Vaccaro

{"title":"Structural design of the iter ec upper launcher","authors":"P. Spaeh, R. Heidinger, K. Kleefeldt, A. Meier, T. Scherer, A. Serikov, D. Strauss, A. Vaccaro","doi":"10.1109/FUSION.2009.5226495","DOIUrl":"https://doi.org/10.1109/FUSION.2009.5226495","url":null,"abstract":"To counteract plasma instabilities, Electron Cyclotron launchers with a total Millimeter-wave power of 20 MW are installed into four of the ITER Upper Ports. Each Mm-wave-system consists of eight transmission lines; a quasi-optical focusing mirror system and two steerable front mirrors to be capable of injecting the beams over the range plasma instabilities are susceptible to occur. The Mm-wave-systems are mounted into a stainless steel cask which has to meet the demands on precise alignment; high-performance cooling for substantial nuclear heat loads; mechanical strength to sustain plasma disruptions and proper nuclear shielding. A structural system of two main components was investigated on a conceptual level. It is composed of the Blanket Shield Module (BSM) and the launcher mainframe. A removable flange connection between the BSM and the main frame provides access to the launcher internals. The entire system is attached to the standard ITER Port interface. Appropriate remote handling capability is also considered. For the BSM and the front segment of the main frame a rigid double wall structure with meandering rectangular cooling channels was designed. The rear part of the main frame consists of a single wall element with individual openings to simplify maintenance access. A shielding concept which serves also as an optical bench for the Millimeter-wave system was developed. Analyses regarding mechanical strength, thermo-hydraulic behavior, baking capability and shielding efficiency were performed. To investigate industrial manufacturing routes, several prototypes of characteristic sections of the BSM and the main frame were manufactured. They are under study at the Launcher Handling Test facility (LHT) at FZK, which is able to simulate different ITER operating conditions. Extensive test series were performed to validate underlying analysis related to temperature distribution, pressure drop within the cooling paths and removal of applied heat loads.","PeriodicalId":236460,"journal":{"name":"2009 23rd IEEE/NPSS Symposium on Fusion Engineering","volume":"59 25","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2009-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"114005938","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

Radiological assessment of target debris in the National Ignition Facility 国家点火装置中目标碎片的放射学评估

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226373

H. Khater, S. Brereton

{"title":"Radiological assessment of target debris in the National Ignition Facility","authors":"H. Khater, S. Brereton","doi":"10.1109/FUSION.2009.5226373","DOIUrl":"https://doi.org/10.1109/FUSION.2009.5226373","url":null,"abstract":"Detailed activation analysis and dose rate calculations are performed for the different materials under consideration for use in the target capsules and hohlraums used during the ignition campaign on the National Ignition Facility. This analysis examined the impact of using Be-Cu and Ge-doped CH capsules on the external dose received by workers during maintenance activities. Five days following a 20 MJ shot, dose rates inside the Target Chamber (TC) due to the two proposed capsule materials are small (∼ 1 mrem/h). Gold and depleted-uranium (DU) are considered as potential hohlraum materials. Following a shot, Au will most probably get deposited on the TC first wall. On the other hand, while noble-gas precursors from the DU are expected to stay in the TC, most of the noble gases are pumped out of the chamber and end up on the cryo-pumps. The dose rates inside the TC due to activated Au or DU, at 5 days following a 20 MJ shot, are about 1 mrem/h. Dose rates in the vicinity of the cryo-pumps (containing noble “fission” gases) drop-off to about 1 mrem/h during the first 12 hours following the shot. A wait period of about 12 hours is recommended before transporting the fission gases outside the Target Bay for radchem analysis.","PeriodicalId":236460,"journal":{"name":"2009 23rd IEEE/NPSS Symposium on Fusion Engineering","volume":"13 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2009-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"122924367","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