NINETEENTH CENTURY MUSIC最新文献_第3页

Upgraded alignment control for the DIII-D Thomson scattering laser system 改进了DIII-D汤姆森散射激光系统的对准控制

IF 0.4 1区艺术学

NINETEENTH CENTURY MUSIC Pub Date : 2002-11-07 DOI: 10.1109/FUSION.2002.1027671

C. Makariou, B. Bray, C. Hsieh

{"title":"Upgraded alignment control for the DIII-D Thomson scattering laser system","authors":"C. Makariou, B. Bray, C. Hsieh","doi":"10.1109/FUSION.2002.1027671","DOIUrl":"https://doi.org/10.1109/FUSION.2002.1027671","url":null,"abstract":"The Thomson scattering system measures electron density and temperature with the aid of eight pulsed Nd:YAG lasers on the DIII-D tokamak. DIII-D is the United States National Fusion Facility for magnetic confinement fusion experiments. The Thomson system probes the tokamak in three separate regions. The measurements from the different regions produce density and temperature profiles during plasma discharges. The laser light must be aimed through the DIII-D vessel with 1 mm of spatial accuracy to produce correct density profiles. Recent upgrades to the alignment system reduce the effort required to perform the initial alignment before plasma operations, and improve the monitoring and control of the alignment. The upgraded hardware allows for monitoring and control of the alignment from the Thomson control room during operations and from multiple key locations along the 35 m long optical path. In future upgrades the adjustment of the mirrors will be automated by utilizing feedback from a computerized beam analysis system that relays beam position information to the control computer. The newly established methods for setting up the YAG beams using the CCD cameras instead of burn paper offer a faster and more reliable method to prepare the system for plasma-operations. The YAG lasers are aimed with repeatable accuracy and any drifts can be detected and corrected during the small warm up period before each shot.","PeriodicalId":44192,"journal":{"name":"NINETEENTH CENTURY MUSIC","volume":null,"pages":null},"PeriodicalIF":0.4,"publicationDate":"2002-11-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"88988578","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":1,"RegionCategory":"艺术学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 1

Modeling of spherical torus plasmas for liquid lithium wall experiments 液体锂壁实验中球形环面等离子体的建模

IF 0.4 1区艺术学

NINETEENTH CENTURY MUSIC Pub Date : 2002-11-07 DOI: 10.1109/FUSION.2002.1027714

R. Kaita, S. Jardin, B. Jones, C. Kessel, R. Majeski, J. Spaleta, R. Woolley, L. Zakharov, B. Nelson, M. Ulrickson

{"title":"Modeling of spherical torus plasmas for liquid lithium wall experiments","authors":"R. Kaita, S. Jardin, B. Jones, C. Kessel, R. Majeski, J. Spaleta, R. Woolley, L. Zakharov, B. Nelson, M. Ulrickson","doi":"10.1109/FUSION.2002.1027714","DOIUrl":"https://doi.org/10.1109/FUSION.2002.1027714","url":null,"abstract":"Liquid metal walls have the potential solve to first-wall problems for fusion reactors, such as heat load and erosion of dry walls, neutron damage and activation, and tritium inventory and breeding. In the near term, such walls can serve as the basis for schemes to stabilize magnetohydrodynamic (MHD) modes. Furthermore, the low recycling characteristics of lithium walls can be used for particle control. Liquid lithium experiments have already begun in the Current Drive eXperiment-Upgrade (CDX-U). Plasmas limited with a toroidally localized limiter have been investigated, and experiments with a fully toroidal lithium limiter are in progress. A liquid surface module (LSM) has been proposed for the National Spherical Torus Experiment (NSTX). In this larger ST, plasma currents are in excess of 1 MA and a typical discharge radius is about 68 cm. The primary motivation for the LSM is particle control, and options for mounting it on the horizontal midplane or in the divertor region are under consideration. A key consideration is the magnitude of the eddy currents at the location of a liquid lithium surface. During plasma start up and disruptions, the force due to such currents and the magnetic field can force a conducting liquid off of the surface behind it. The Tokamak Simulation Code (TSC) has been used to estimate the magnitude of this effect. This program is a two dimensional, time dependent, free boundary simulation code that solves the MHD equations for an axisymmetric toroidal plasma. From calculations that match actual ST equilibria, the eddy current densities can be determined at the locations of the liquid lithium. Initial results have shown that the effects could be significant, and ways of explicitly treating toroidally local structures are under investigation.","PeriodicalId":44192,"journal":{"name":"NINETEENTH CENTURY MUSIC","volume":null,"pages":null},"PeriodicalIF":0.4,"publicationDate":"2002-11-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"86395765","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":1,"RegionCategory":"艺术学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 1

Overview of the TFTR D&D program TFTR研发计划概述

IF 0.4 1区艺术学

NINETEENTH CENTURY MUSIC Pub Date : 2002-11-07 DOI: 10.1109/FUSION.2002.1027736

S. Raftopoulos, G. Barnes, J. Chrzanowski, J. Dimattia, R. Fedder, D. Gallagher, E. Gilsenan, G. Gettelfinger, R. Jakober, J. Laneski, P. Lamarche, R. Lindenberg, R. Parsells, E. Perry, K. Rule, J. Semler, J. Stacy, M. Viola, I. Zatz, W. Zimmer

引用次数: 4

Analysis of discharge characteristics of the inertial electrostatic confinement fusion using a particle code with Monte Carlo collision scheme 用蒙特卡罗碰撞格式粒子码分析惯性静电约束聚变的放电特性

IF 0.4 1区艺术学

NINETEENTH CENTURY MUSIC Pub Date : 2002-11-07 DOI: 10.1109/FUSION.2002.1027677

T. Sakai, K. Noborio, Y. Yamamoto

引用次数: 7

Structural analyses and preliminary design of HT-7U cryostat HT-7U低温恒温器结构分析与初步设计

IF 0.4 1区艺术学

NINETEENTH CENTURY MUSIC Pub Date : 2002-11-07 DOI: 10.1109/FUSION.2002.1027715

Junhui Yu, S. Wu, Y. Song, P. Weng

引用次数: 2

ARIES-AT magnet systems 白羊- at磁体系统

IF 0.4 1区艺术学

NINETEENTH CENTURY MUSIC Pub Date : 2002-11-07 DOI: 10.1109/FUSION.2002.1027723

L. Bromberg, T. Brown, F. Dahlgren, P. Heitzenroeder

引用次数: 22

Design overview of the KSTAR magnet structures KSTAR磁体结构设计概述

IF 0.4 1区艺术学

NINETEENTH CENTURY MUSIC Pub Date : 2002-11-07 DOI: 10.1109/FUSION.2002.1027722

Y. Oh, C.H. Choi, J. Sa, H. Ahn, K. J. Cho, Y.M. Park, Y.S. Kim, K. Kim, D.K. Lee, S. Cho, N. Her, M. Kwon, J. Bak, G.S. Lee

{"title":"Design overview of the KSTAR magnet structures","authors":"Y. Oh, C.H. Choi, J. Sa, H. Ahn, K. J. Cho, Y.M. Park, Y.S. Kim, K. Kim, D.K. Lee, S. Cho, N. Her, M. Kwon, J. Bak, G.S. Lee","doi":"10.1109/FUSION.2002.1027722","DOIUrl":"https://doi.org/10.1109/FUSION.2002.1027722","url":null,"abstract":"The magnet structure system of the Korea Superconducting Tokamak Advanced Research (KSTAR) device consists of 16-segmented toroidal field (TF) coil structures encasing each D-shaped TF coil, a central solenoid (CS) structure surrounding 4 pairs of CS coils, modular poloidal field (PF) coil structures supporting each PF coil in 8 or 16 places, and a gravity support. The engineering design of the magnet structures has been conducted with related electromagnetic load calculations and structural analyses for various operation scenarios. A prototype TF coil structure will be fabricated to check the manufacturing feasibility. A prototype magnet supporting post has been fabricated and tested at 80 K up to 15,000 cycles of vertical load under 80 tons. In addition to the magnet structure development, winding and heat treatment of a real-sized prototype TF coil have been finished without any defect such as SAGBO. The fabrication of the coil will be completed by the middle of 2002. As an interface of the magnet system, a cryogenic facility and a current feeder system have been designed.","PeriodicalId":44192,"journal":{"name":"NINETEENTH CENTURY MUSIC","volume":null,"pages":null},"PeriodicalIF":0.4,"publicationDate":"2002-11-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"76070815","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":1,"RegionCategory":"艺术学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 5

ECRH power injection in TORE SUPRA ECRH功率注入TORE SUPRA

IF 0.4 1区艺术学

NINETEENTH CENTURY MUSIC Pub Date : 2002-11-07 DOI: 10.1109/FUSION.2002.1027704

M. Lennholm, G. Agarici, A. Barbuti, G. Berger-by, F. Bouquey, J. Clary, C. Darbos, R. Dumont, G. Giruzzi, M. Jung, R. Magne, D. Roux, J. Ségui, X. Zou

引用次数: 3

Impact of low PRF tritium permeation barriers-on the water cooled lead lithium blanket: A safety analysis 低PRF氚渗透屏障对水冷铅锂包层的影响:安全性分析

IF 0.4 1区艺术学

NINETEENTH CENTURY MUSIC Pub Date : 2002-11-07 DOI: 10.1109/FUSION.2002.1027711

I. Ricapito, G. Cambi, A. Aiello, G. Benamati, O. Kveton, M. Futterer

{"title":"Impact of low PRF tritium permeation barriers-on the water cooled lead lithium blanket: A safety analysis","authors":"I. Ricapito, G. Cambi, A. Aiello, G. Benamati, O. Kveton, M. Futterer","doi":"10.1109/FUSION.2002.1027711","DOIUrl":"https://doi.org/10.1109/FUSION.2002.1027711","url":null,"abstract":"A summary is here presented concerning the first results in evaluating the safety features of the European water-cooled lead lithium blanket in which tritium permeation barriers on the external surface of the breeder cooling pipes are not used or, if used, a lower efficiency is required for them. As a consequence, in this design concept, a significant amount of tritium must be recovered through the water detritiation system. The technical and economical feasibility of such a tritium management strategy was demonstrated up to a tritium permeation rate of 10+15 g/day, accepting, at the same time, a higher tritium activity in the primary coolant in order not to overload the water detritiation system. A safety analysis has then been performed to evaluate the impact of a higher tritium specific activity in the primary coolant, both in normal operation and in accidental condition. Tritium release to the environment in case of a LOCA was found to satisfy the limits recommended by the ITER Project Design Guidelines for accidental tritium release, while the respect of the limits for chronic release strongly depends on the water leak rate from the primary to the secondary circuit.","PeriodicalId":44192,"journal":{"name":"NINETEENTH CENTURY MUSIC","volume":null,"pages":null},"PeriodicalIF":0.4,"publicationDate":"2002-11-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"76936353","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":1,"RegionCategory":"艺术学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Towards ITER construction 迈向ITER建设

IF 0.4 1区艺术学

NINETEENTH CENTURY MUSIC Pub Date : 2002-11-07 DOI: 10.1109/FUSION.2002.1027629

R. Aymar

引用次数: 5