2009 23rd IEEE/NPSS Symposium on Fusion Engineering最新文献_第4页

Preliminary design of high temperature lithium-lead blanket with SiC cooling panel SiC冷却板高温锂铅包层初步设计

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226508

M. Ichinose, Y. Yamamoto, K. Noborio, Y. Takeuchi, S. Konishi

引用次数: 7

Heat transfer of free surface MHD-flow with a wall of non-uniform electrical conductivity 具有非均匀导电性壁的自由表面mhd流动的传热

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226450

Hulin Huang, Bo Li

{"title":"Heat transfer of free surface MHD-flow with a wall of non-uniform electrical conductivity","authors":"Hulin Huang, Bo Li","doi":"10.1109/FUSION.2009.5226450","DOIUrl":"https://doi.org/10.1109/FUSION.2009.5226450","url":null,"abstract":"The non-uniform electrical conductivity distribution of a channel wall can create alternate Lorentz forces along spanwise direction, which can effectively produce flow disturbance, promote mixture, reduce the thickness of boundary layer, and enhance heat transfer in Magnetohydrodynamic (MHD) flow. So the heat transfer performances enhanced by some conducting strips aligned with the mean flow direction on the insulating wall for a free surface MHD-flow are simulated numerically in this paper. The flow behaviors, heat transfer coefficients, friction factors and pressure drops are presented under different Hartmann numbers. Results show that, in the range of Hartmann numbers 30≤Ha≤100, the wall with nonuniform conductivity can achieve heat transfer enhancements (Nu/Nu0) of about 1.2 to 1.6 relative to the insulating wall with negligible friction rise. The modules with three or five conducting strips can obtain better enhancement effect in this paper. Particularly, the heat transfer coefficient increases monotonically with Hartmann numbers increasing. Therefore, the enhancement purpose for MHD flow at high Hartman number is pronounced.","PeriodicalId":236460,"journal":{"name":"2009 23rd IEEE/NPSS Symposium on Fusion Engineering","volume":"18 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":"127818106","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

Dynamic response of the ITER vacuum vessel to electromagnetic loads during VDEs vde过程中ITER真空容器对电磁载荷的动态响应

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226477

C. Bachmann, G. Sannazzaro, M. Sugihara, Y. Gribov, K. Ioki, V. Riccardo, A. Belov, E. Lamzin

{"title":"Dynamic response of the ITER vacuum vessel to electromagnetic loads during VDEs","authors":"C. Bachmann, G. Sannazzaro, M. Sugihara, Y. Gribov, K. Ioki, V. Riccardo, A. Belov, E. Lamzin","doi":"10.1109/FUSION.2009.5226477","DOIUrl":"https://doi.org/10.1109/FUSION.2009.5226477","url":null,"abstract":"During vertical displacement events (VDEs) plasma halo currents can flow partly through the passive structure. Additionally induced currents occur in the passive structure. Due to these electrical currents, major electromagnetic forces act on the passive structures and hence on the vacuum vessel (VV). As these forces change in time the vessel response is dynamic. This response determines important design drivers such as the reaction forces at the vessel supports, the vessel displacements and stress levels in the vessel structure, and it affects all components attached to the vessel. It is expected that the most severe dynamic response of the vessel occurs during asymmetric VDEs with slow current quench. Experiments on existing tokamak machines have shown that asymmetric loads can rotate around the vertical machine axis. This possible rotation is considered here. Using the finite element (FE) method the dynamic response of the vessel was analyzed in full transient dynamic analyses for the worst case VDEs according to the ITER VV load specification [2]. A 360° FE model of the VV is used since the loads are partly asymmetric. One major difficulty in this assessment was to predict how the sideways load is shared between three simultaneously acting support types. Attention was therefore given to the modeling of the VV supports including the coupling effect with the toroidal magnetic field.","PeriodicalId":236460,"journal":{"name":"2009 23rd IEEE/NPSS Symposium on Fusion Engineering","volume":"15 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":"134492265","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

Simulation experiment of thermal transient events in ITER by use of magneti zed coaxial plasma gun 利用磁化同轴等离子体枪进行ITER热瞬态事件的模拟实验

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226429

Y. Kikuchi, R. Nakanishi, M. Nakatsuka, N. Fukumoto, M. Nagata

引用次数: 0

An intermediate power amplifier upgrade for 40 to 80 Mhz for the alcator C-Mod ICRF transmitters 为C-Mod ICRF发射机升级40至80 Mhz的中间功率放大器

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226410

A. Binus, S. Wukitch, Y. Lin, R. Murray, A. Pfeiffer, D. Gwinn

引用次数: 1

Upgrade of the JET tangential gamma-ray spectrometer. Conceptual design JET切向伽玛射线光谱仪的升级。概念设计

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226468

V. Zoita, T. Craciunescu, I. Tiseanu, M. Curuia, S. Soare, M. Anghel, V. Braic, M. Braic, G. Gros, V. Kiptily, T. Edlington, P. Prior, S. Sanders, B. Syme, L. Rı́os, P. Blanchard, A. Murari

{"title":"Upgrade of the JET tangential gamma-ray spectrometer. Conceptual design","authors":"V. Zoita, T. Craciunescu, I. Tiseanu, M. Curuia, S. Soare, M. Anghel, V. Braic, M. Braic, G. Gros, V. Kiptily, T. Edlington, P. Prior, S. Sanders, B. Syme, L. Rı́os, P. Blanchard, A. Murari","doi":"10.1109/FUSION.2009.5226468","DOIUrl":"https://doi.org/10.1109/FUSION.2009.5226468","url":null,"abstract":"A conceptual design for the upgrade of the JET tangential gamma-ray spectrometer (TGRS) has been carried out. The main design target for the TGRS upgrade is to maximize the signal-to background ratio at the spectrometer detector, the ratio being defined in terms of the plasma emitted gamma radiation and the gamma-ray background. A complex system of collimators and shields for both the neutron and gamma radiations define the spectrometer field of view. Two tandem collimators determine the field of view through the tokamak plasma. The entrance aperture to the penetration in the JET Torus Hall south wall is defined by a neutron shield. Two gamma-ray shields together with the existing concrete collimator determine the field of view at the bismuth germanate (BGO) gamma-ray detector. One of the gamma-ray shields (with an embedded neutron attenuator) can be remotely moved in and out of the detector line of sight thus providing flexibility in definition of the neutron and gamma-ray fields at the BGO detector. Neutron attenuators using lithium hydride (LiH) with natural isotopic composition (that meets the requirements for gamma-ray transparency) could provide the necessary attenuation factors (approximately 104 for the 2.45 MeV neutrons and 102 for the 14.1 MeV neutrons). A hot pressing technology has been proposed for the construction of the lithium hydride attenuators. The performance of a simplified geometry TGRS has been evaluated by preliminary neutron and photon transport calculations and the results show that the design parameters could be attained.","PeriodicalId":236460,"journal":{"name":"2009 23rd IEEE/NPSS Symposium on Fusion Engineering","volume":"239 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":"116065828","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

Application of Magnetic Energy Recovery Switch (MERS) to power supply systems of nuclear fusion device 磁能量回收开关在核聚变装置供电系统中的应用

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226371

T. Matsukawa, T. Isobe, R. Shimada, H. Tsutsui, S. Tsuji-Iio

{"title":"Application of Magnetic Energy Recovery Switch (MERS) to power supply systems of nuclear fusion device","authors":"T. Matsukawa, T. Isobe, R. Shimada, H. Tsutsui, S. Tsuji-Iio","doi":"10.1109/FUSION.2009.5226371","DOIUrl":"https://doi.org/10.1109/FUSION.2009.5226371","url":null,"abstract":"Electric power circuits applied with Magnetic Energy Recovery Switch (MERS) are proposed to be used for power supply systems of nuclear fusion device. MERS basically consists of four self-commutated power electronics elements as switching unit and one capacitor. MERS can be operated with on-off switching of four power electronics elements by controlling their gate signals to output its electric power in DC or AC. As poloidal ield coil power supply, it is required that the coil current is slightly high DC one and controlled to sustain plasma current and/or configuration. When MERS assist the conventional AC/DC converter of poloidal field coil power supply, it is expected that the voltage rating of AC/DC converter would be reduced and the controllability of coil current would be also improved. As RWM (Resistive Wall Mode) suppressing coil power supply, it is required that the coil current should be pulsatile one in wide frequency range and controlled more rapidly to stabilize the plasma instability. When MERS is applied to RWM suppressing coil power supply, it will be promised that the controllability of coil current is improved with resonant operation of MERS and RWM suppressing coil itself.","PeriodicalId":236460,"journal":{"name":"2009 23rd IEEE/NPSS Symposium on Fusion Engineering","volume":"31 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":"124829010","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

Numeric implementation of two-phase tritium transport models for natural helium nucleated bubbles in lead-lithium. Implications for HCLL breeding blanket channels 铅锂中天然氦核气泡两相氚输运模型的数值实现。对HCLL繁殖毯状通道的启示

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226440

J. Fradera, L. Batet, E. M. de les Valls, L. Sedano

{"title":"Numeric implementation of two-phase tritium transport models for natural helium nucleated bubbles in lead-lithium. Implications for HCLL breeding blanket channels","authors":"J. Fradera, L. Batet, E. M. de les Valls, L. Sedano","doi":"10.1109/FUSION.2009.5226440","DOIUrl":"https://doi.org/10.1109/FUSION.2009.5226440","url":null,"abstract":"Tritium (T) self-sufficiency requirement is linked to high helium (He) production rates in a D-T fusion reactor breeding blanket (BB). In Liquid Metal (LM) BB concepts, large local He concentrations may result in bubble formation, which might have an enormous influence in the components performance. The present work states that such a possibility is not remote in a Helium Cooled Lithium Lead (HCLL) BB design. Bubbles could act as an effective T sink, reducing T partial pressure in the bulk LM and thus affecting T inventory control. Models for He nucleation, bubble growth and transport, along with T absorption and transport, have been implemented in the CFD code OpenFOAM®. Classical Nucleation Theory has been used for He nucleation. In the growth model, bubble growth is controlled by diffusion (it is assumed that bubbles are small enough); the mean radius approach has been implemented in order to save computational time. Tritium absorption is modelled using the Lewis-Whitman film theory. He and T concentration maps have been calculated for a HCLL single channel. Results show the effect of gas bubbles on T concentration. A pressure driven nucleation case have also been calculated. Work presented is a first step towards the quantification of the complex phenomena involved in He nucleation in LM and its effects on T inventory within a BB design.","PeriodicalId":236460,"journal":{"name":"2009 23rd IEEE/NPSS Symposium on Fusion Engineering","volume":"29 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":"124963466","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

Development of joining processes and fabrication of US first wall qualification mockups for ITER ITER连接工艺的开发和美国首个壁体验证模型的制作

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226492

S. Goods, J. Puskar, R. M. Watson, M. Ulrickson

引用次数: 1

Beamline optimization for 100keV diagnostic neutral beam (DNB) injector for ITER ITER 100keV诊断中性束(DNB)注入器光束线优化

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI: 10.1109/FUSION.2009.5226483

M. Bandyopadhyay, M. Singh, C. Rotti, A. Chakraborty, R. Hemsworth, B. Schunke

{"title":"Beamline optimization for 100keV diagnostic neutral beam (DNB) injector for ITER","authors":"M. Bandyopadhyay, M. Singh, C. Rotti, A. Chakraborty, R. Hemsworth, B. Schunke","doi":"10.1109/FUSION.2009.5226483","DOIUrl":"https://doi.org/10.1109/FUSION.2009.5226483","url":null,"abstract":"The 100 kV negative hydrogen ion source based Diagnostic Neutral Beam (DNB) injector, which forms a part of the IN Procurement Package for ITER, targets a delivery of ∼ 18–20A of neutral hydrogen atom beam current into the ITER torus for charge exchange resonance spectroscopy (CXRS) diagnostics. Considering stripping losses, ∼ 70A negative ion current is required to be extracted from the ion source, which leads to a production of 60 A of accelerated ion beam. Subsequent process of neutralization, electrostatic ion separation and transport to the duct leads to a large separation between the points of generation of ion beam to the point of delivery of the neutral beam into the Torus (∼ 23 m). This forms one of the most important constraints for the transport of neutral beams to ITER. The requirements are not only for a stringent control over ion optics, the transport to electrostatic separator, minimum loss of beam due to intercepting elements, low reionization loss, focusing to control interception losses, adequate compensation of residual magnetic fields to overcome magnetic field induced deflections also forms important design issues for a reasonable transmission efficiency.","PeriodicalId":236460,"journal":{"name":"2009 23rd IEEE/NPSS Symposium on Fusion Engineering","volume":"74 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":"126160355","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: 10