NbTi/Cu-Ni/Cu三组元超导磁体的快速励磁特性

采用强迫励磁和在额定电流下突然合闸两种励磁方式,测量了Nb-Ti/Cu-Ni/Cu三组元超导体的稳定性。试验表明,与纯铜为基的Nb-Ti磁体相比,三组元超导磁体的H_c值高得多。     

Preliminary Engineering Design of Toroidal Field Magnet System for Superconducting Tokamak HT-7U

1.IntroductionHT-7Usuperconductingtokamakisanationalsci-entificresearchprojectofChina.ThislargefusionexperimentaldevicewillbebuiltinthelnstituteofPlasmaPhyslcsofChineseAcademyofSciences.ThemissionofHT-7Uistodevelopthescientificba-sisforacontinuouslyoperatingtokamakfusionreac-tor,achievingasteadystateandanextremelylongpuIseoperatlonwlthhigh-betadouble-null,aswellassingle-nullplasmasatfllllcllrrent.HT-7Uisafullsuperconductingtokamakdevlce.ltstoroidalfieldsystemisoneoftheimportantpartsofthe…     

Evaluation of AC Losses for HT-7U CICC on Plasma Disruption

1. IntroductionThe reduction of AC loss is one of the most important items of superconducting TF and PF coils.Because AC loss affects the stability of CICC, thestability of TF and PF coil is affected by AC loss.The high current multi--strand conductors used intokaxnaks for fusion can be subjected to pulsed magnetiC field, the variations of which would induceinter--strand coupling currents. These currents createJoule heat loss, (i.e. the so--called AC losses) which' is characterized by…     

Trial Manufacture of a 30 m Cable-in-Conduit-Conductor (CICC) for HT-7U

1.IntroductionTherearetwodifferentkindsofconfiguration,i.e.,thesoakingandtheCICCtype,beingusedrespec-tivelyforthecoilsoflongitudinafieldandpoloidalfield.ThetaskassignedtothedevelopmentofCICCistoinsertagh21mmsuperconductingcablethrougha3Om,of26x1.5mmconduitmadeof3l6LSSma-terial,withagapbeing2.omminbetween.l92strandsofofo.65mmNbTiwirearetwistedwithl92strandsofgho.85mmCuwireuptoasupercon-ductingcableina4x4x4x6format,onwhichtheoutersurfaceiswraPpedwithao.1mmthickstain-lessstee1tape(Fig.1).A…     

结构实体质量检验中注意的几个问题

首先指出结构实体检验是对结构工程的基本技术要求,其代表结构工程的基本特性,阐述了结构实体检验的主要依据,分析了混凝土强度、钢筋间距、钢筋保护层厚度、砌体砂浆强度等检验中应注意的问题,以确保结构安全。     

Investigation on the Relation of CICC Stability Margin to Mass Flow Rate and Operating Temperature of Helium

1. IntroductionThe conductor which is used for thermonuclear fusion reactors must guarantee high current density,excellent transient stability and mechanical stabilityof the magnet structure. The application of CICChas provided these advantages for the design alldconstruction of superconducting magnets, Experimental results of the stability margin of CICC madeby ITER show that the stability margin is largelydependent on operating mass flow. The numericalsimulation was performed with the s…     

New CICC Design Versions with High Copper Fraction for HT-7U Tokamak

1. IntroductionHT-7U TOkamak is a fusion experiment devicewith a major radius of 1.7 m and a minor radiusof 0.4 x 0.72 m (D--shaped cross--section of plasma).The magnets of the tokamak consist of 16 D--shapedcoils for the toroidal field (TF), 6 coils for the central solenoid, and another 6 coils for divertor, shaping and equilibrium fields. Fig. 1 shows the TF andpololdal field (PF) coil arrangement. As CICC hasmany advantages of excellent winding insulation andintegrity, lower ac losse…