2007 IEEE 22nd Symposium on Fusion Engineering最新文献_第2页

Development of Water Hydraulic Remote Handling System for Divertor Maintenance of ITER ITER导流器维修水液压远程操作系统的研制

2007 IEEE 22nd Symposium on Fusion Engineering Pub Date : 2007-06-17 DOI: 10.1109/FUSION.2007.4337865

A. Muhammad, S. Esqué, J. Mattila, M. Tolonen, P. Nieminen, O. Linna, M. Vilenius, M. Siuko, J. Palmer, M. Irving

引用次数: 11

Finite Element Stress Analysis OF ITER Module 13 ITER模块13的有限元应力分析

2007 IEEE 22nd Symposium on Fusion Engineering Pub Date : 2007-06-17 DOI: 10.1109/FUSION.2007.4337946

J. Garde, D. Youchison, G. Natoni, J. Bullock, T. Tanaka, M. Ulrickson, M. Narula, A. Ying, M. Sawan, P. Wilson

引用次数: 1

Design of an experimental facility to study convection in liquid lithium 研究液态锂对流的实验装置设计

2007 IEEE 22nd Symposium on Fusion Engineering Pub Date : 2007-06-17 DOI: 10.1109/FUSION.2007.4337874

M. Jaworski, D. Ruzic

引用次数: 2

FPGA-Based Pulse-Oriented Digital Acquisition System For Nuclear Detectors 基于fpga的核探测器脉冲数字采集系统

2007 IEEE 22nd Symposium on Fusion Engineering Pub Date : 2007-06-17 DOI: 10.1109/FUSION.2007.4337920

M. Riva, B. Esposito, D. Marocco

{"title":"FPGA-Based Pulse-Oriented Digital Acquisition System For Nuclear Detectors","authors":"M. Riva, B. Esposito, D. Marocco","doi":"10.1109/FUSION.2007.4337920","DOIUrl":"https://doi.org/10.1109/FUSION.2007.4337920","url":null,"abstract":"Neutron/gamma-ray pulse shape discrimination (PSD) is a common technique applied to detectors (liquid organic scintillators) employed in neutron diagnostics for fusion plasmas. For example, NE213 scintillators, coupled with analogue PSD modules are in operation at JET (Joint European Torus) in the radial and vertical neutron camera and also in a compact neutron spectrometer system. However, these analogue systems present several drawbacks, such as limited count rate (typically ~0.2 MHz) and no reprocessing capability. ENEA-Frascati has therefore started to develop digital solutions to offer increased performances, both using commercial digital boards and developing in-house new digital architectures. This article illustrates the capabilities of the new digital architecture with high acquisition speed (200 Msamples/s) and high dynamic range (14 bit). The novel DWDA (Dynamic Window Data Acquisition) technique will be shown: the incoming signal is acquired only when the signal trespasses a threshold and the duration of the acquisition is variable so that every pulse in the current time window is sampled and acquired. Some experimental results will be presented.","PeriodicalId":124369,"journal":{"name":"2007 IEEE 22nd Symposium on Fusion Engineering","volume":"30 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2007-06-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"125127723","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

Conceptual Design of the ICRH and LHCD Systems for FT-3 FT-3的ICRH和LHCD系统概念设计

2007 IEEE 22nd Symposium on Fusion Engineering Pub Date : 2007-06-17 DOI: 10.1109/FUSION.2007.4337936

F. Mirizzi, A. Cardinali, R. Maggiora, L. Panaccione, G. Ravera, A. Tuccillo

{"title":"Conceptual Design of the ICRH and LHCD Systems for FT-3","authors":"F. Mirizzi, A. Cardinali, R. Maggiora, L. Panaccione, G. Ravera, A. Tuccillo","doi":"10.1109/FUSION.2007.4337936","DOIUrl":"https://doi.org/10.1109/FUSION.2007.4337936","url":null,"abstract":"A conceptual design of a new tokamak has been elaborated by the Fusion Department of ENEA (Frascati, Italy). The machine, so far called FT-3, aims to study burning plasmas and to prepare ITER scenarios thus hoping to be approved to be part of the accompanying program. FT-3 could start operations by the end of the ITER construction. It will be able of high plasma performance in a dimensionless parameter range close to that of ITER with pulse length long enough to address steady state physics. FT-3 will work with Deuterium plasmas and will simulate the alpha particle dynamics by using fast ions accelerated by powerful heating and current drive systems. Main heating source will be an Ion cyclotron radio frequency (ICRF) system that, in its initial configuration, will couple to the plasma 20 MW (extendible to 30 MW) at 60-90 MHz. To address Advanced Scenarios and steady state physics at high plasma density (ne ges 1020 m-3 ) it is foreseen the installation of a lower hybrid (LH) system to control the current profile via off axis current drive (CD). A minimum coupled power of 6 MW is considered necessary to achieve the expected scenarios. The LH launching structure is based on the PAM concept, which coupling properties have been recently demonstrated on the Frascati Tokamak Upgrade (FTU). A conceptual analysis of the two systems is given.","PeriodicalId":124369,"journal":{"name":"2007 IEEE 22nd Symposium on Fusion Engineering","volume":"49 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2007-06-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"133367846","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

Phased Array Ultrasonic Non-Destructive Evaluation of ITER Plasma Facing Components ITER等离子体面元件的相控阵超声无损评价

2007 IEEE 22nd Symposium on Fusion Engineering Pub Date : 2007-06-17 DOI: 10.1109/FUSION.2007.4337883

V. Lupien

引用次数: 0

Low Pressure Operation of Radially Convergent Beam Fusion Using Differentially-Pumped Ion Sources 采用差分泵浦离子源的径向会聚束聚变低压运行

2007 IEEE 22nd Symposium on Fusion Engineering Pub Date : 2007-06-17 DOI: 10.1109/FUSION.2007.4337898

K. Yamauchi, K. Nozaki, M. Watanabe, A. Okino, E. Hotta

{"title":"Low Pressure Operation of Radially Convergent Beam Fusion Using Differentially-Pumped Ion Sources","authors":"K. Yamauchi, K. Nozaki, M. Watanabe, A. Okino, E. Hotta","doi":"10.1109/FUSION.2007.4337898","DOIUrl":"https://doi.org/10.1109/FUSION.2007.4337898","url":null,"abstract":"Radially convergent beam fusion (RCBF) has been studied for practical use as a portable neutron/proton source for various applications such as landmine detection and positron emission tomography. In a conventional RCBF device using a glow discharge, the neutron/proton production rate is proportional to the cathode current because beam-background reactions are dominant in contrast with the original RCBF concept. However, since the neutron/proton production rate of beam-beam reactions is proportional to the cathode current squared, beam-beam reactions have a potential to increase the neutron/proton production rate in a high cathode current region. In this study, a new RCBF system using differentially-pumped ion sources was designed for the low pressure operation without the glow discharge. In the RCBF chamber, a cylindrical grid cathode is concentrically placed on the axis of a cylindrical mesh anode, and two ion sources are oppositely mounted around the mesh anode. The ion sources allow the RCBF device to be operated at a pressure of 10-4 Torr in the RCBF chamber, which is much lower than that of 10-1 Torr in the ion sources. Generated ions in the ion sources are extracted through each orifice by the pressure gradient and the extraction electric field, and then accelerated to the RCBF cathode. At first, a performance as differential pumping system and discharge characteristics of ion sources were investigated. Then, the neutron production rate at a lower pressure compared with that of a conventional RCBF device was measured. Neutron production rate at a pressure of 0.30 mTorr was proportional to the ion current to the power of 1.19-1.23. This implies that the fraction of beam-beam reactions was increased by the reduction of background pressure in the RCBF chamber.","PeriodicalId":124369,"journal":{"name":"2007 IEEE 22nd Symposium on Fusion Engineering","volume":"38 42","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2007-06-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"114052988","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

A Fast visible camera Divertor-imaging diagnostic on DIII-D DIII-D上的快速可见相机转向成像诊断

2007 IEEE 22nd Symposium on Fusion Engineering Pub Date : 2007-06-17 DOI: 10.1109/FUSION.2007.4337940

A. Roquemore, R. Maingi, C. Lasnier, N. Nishino, T. Evans, M. Fenstermacher, A. Nagy

{"title":"A Fast visible camera Divertor-imaging diagnostic on DIII-D","authors":"A. Roquemore, R. Maingi, C. Lasnier, N. Nishino, T. Evans, M. Fenstermacher, A. Nagy","doi":"10.1109/FUSION.2007.4337940","DOIUrl":"https://doi.org/10.1109/FUSION.2007.4337940","url":null,"abstract":"In recent campaigns, the photron ultima SE fast framing camera has proven to be a powerful diagnostic when applied to imaging divertor phenomena on the national spherical torus experiment (NSTX). Active areas of NSTX divertor research addressed with the fast camera include identification of types of EDGE localized modes (ELMs)[1], dust migration, impurity behavior and a number of phenomena related to turbulence. To compare such edge and divertor phenomena in low and high aspect ratio plasmas, a multi-institutional collaboration was developed for fast visible imaging on NSTX and DIII-D. More specifically, the collaboration was proposed to compare the NSTX small type V ELM regime[2] and the residual ELMs observed during Type I ELM suppression with external magnetic perturbations on DIII-D[3]. As part of the collaboration effort, the photron camera was installed recently on DIII-D with a tangential view similar to the view implemented on NSTX, enabling a direct comparison between the two machines. The rapid implementation was facilitated by utilization of the existing optics that coupled the visible spectral output from the divertor vacuum ultraviolet UVTV system, which has a view similar to the view developed for the divertor tangential TV camera[4]. A remote controlled filter wheel was implemented, as was the radiation shield required for the DIII-D installation. The installation and initial operation of the camera are described in this paper, and the first images from the DIII-D divertor are presented.","PeriodicalId":124369,"journal":{"name":"2007 IEEE 22nd Symposium on Fusion Engineering","volume":"32 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2007-06-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"114466983","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

Flow Optimization Studies for the ITER Shield Modules ITER屏蔽模块流动优化研究

2007 IEEE 22nd Symposium on Fusion Engineering Pub Date : 2007-06-17 DOI: 10.1109/FUSION.2007.4337896

G. Natoni, D. Youchison, M. Ulrickson, M. Sawan

{"title":"Flow Optimization Studies for the ITER Shield Modules","authors":"G. Natoni, D. Youchison, M. Ulrickson, M. Sawan","doi":"10.1109/FUSION.2007.4337896","DOIUrl":"https://doi.org/10.1109/FUSION.2007.4337896","url":null,"abstract":"A 3-d, 4-channel prototypical model representing a subset of an ITER neutron shield module was analyzed using computational fluid dynamics. We used this model to optimize the radial gaps in the coaxial flow drivers along with the depth of the radial holes or channels in the stainless steel modules. In addition to redirecting the flow first to the back of the module and then to the front, the flow drivers increase the pressure drop in the radial tubes to allow for more uniform flow distribution from the back-drilled manifolds. They also increase the fluid velocity near the wall for improved heat transfer. We sized the flow drivers to allow for 2, 3 and 4-millimeter (mm) gaps along the annuli. The depths of the radial channels below the manifold were 10, 15, 20, 25, and 30 mm for each of the 2, 3, and 4 mm radial gaps. The objective of the study was to ascertain if a fixed 90-mm length on the bottom flow driver could be utilized for radial channels of varying depth below the back-drilled manifold and still provide adequate cooling for the neutron thermal load. Our group also performed an optimization of the gap around the tee-vane in the shield module front header. Tee-vane gaps of 1, 2 and 3 mm were studied to assess the flow bypass and wall velocities at the end of the model. In this article, we present the results of a full matrix of flow simulations using the CFdesign CFD package. The study indicates that a 90-mm-long flow driver with a 4-mm radial gap can keep the steel around the radial tubes sufficiently cool up to 30 mm beneath the back-drilled manifold. We also discovered that flow bypass through the end gap on the tee-vane is relatively small and has little effect on cooling of the front cover plate for gap sizes as large as 3 mm.","PeriodicalId":124369,"journal":{"name":"2007 IEEE 22nd Symposium on Fusion Engineering","volume":"231 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2007-06-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"115805916","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

Preliminary Probabilistic Safety Assessment of Chinese Dual Functional Lithium Lead Test Blanket Module System for ITER 中国ITER双功能锂铅试验包层模块系统的初步概率安全性评价

2007 IEEE 22nd Symposium on Fusion Engineering Pub Date : 2007-06-17 DOI: 10.1109/FUSION.2007.4337911

L. Hu, Y. Wu, J. Wang, S. Wang

引用次数: 3