紧凑型双匝电磁轨道炮及多发填弹器的研制

该文介绍了由脉冲补偿电机供能的连发电磁轨道炮,该连发炮由自动填弹控制电源控制的步进电动机驱动“WJ蜗杆凸轮步进机构”,以高定位精度分度驱动转膛式连发机构,将弹丸连续触发,经过渡段进入双匝加强型轨道炮进一步加速后出腔,初速V=250m/s     

基于场反位形的磁约束氘氘脉冲聚变中子源方案设计

聚变中子源可以真实反映材料在聚变中子辐照下的特性变化,对于开展聚变堆材料测试具有重要意义。基于加速器打靶原理的国际聚变材料辐照装置（IFMIF）与理想聚变中子源在聚变中子能谱等方面仍有一定差异,因此需对聚变中子源方案进行新的思索。本文围绕磁约束聚变中子源开展了磁场位形、加热方案设计与相关计算,分析了场反等离子体在两级级联磁压缩后的等离子体温度、密度演化过程及相应的中子产额,并研究了考虑双流体效应与有限拉莫尔半径效应后场反等离子体倾斜模、旋转模等磁流体不稳定性的抑制情况,最终给出了氘氘脉冲聚变中子源的关键物理参数。研究结果表明,该中子源有望获得年均2 MW/m2以上的高通量密度的聚变中子,能够满足商业聚变示范堆材料测试要求;经功率估算显示,基于场反位形进行两级级联磁压缩的新型聚变中子源方案还具备成为氘氘脉冲聚变能源的应用前景。     

微相增韧低温工程用环氧树脂胶粘剂的研究

优化了自主开发的适用于低温工程的环氧树脂胶粘剂的配方组分和固化条件,测试了其低温力学和真空性能,分析了其动态热力曲线和断口表面形貌,研究了该低温用环氧树脂胶粘剂的增韧机理,证明在聚醚/聚氨脂类增韧剂增韧的环氧树脂-胺固化体系中,能形成微相的两相结构,对具有良好的低温性能起了关键作用.     

Linear Buckling Analysis of the HT-7U Vacuum Vessel

1. IntroductionHT-7U superconducting Tokamak, as a nationalproject, is an advanced steady-state plasma exper-imental device to be built in 2Oo3. Now all kindsof engineering design have been begun. The vac-uum vessel is one of the key parts for HT-7U de- vice, which can provide not only a clean and ultra-high vacuum env1ronment in the operatlon of plasmafor the production quilibrium and heating of thelasma, but also reliable supporting structure andvarious channels for a series of equipme…     

氢冰弹丸测速仪的研制

作为未来核聚变反应堆燃料添加及目前对高温等离子体进行诊断的有效工具之一的氢冰弹丸注入,其物理上要求给出的弹丸注入速度参数的精度在2%以内。通过采用狭缝式辐射光源、阵列式分束光纤接收的方法来提高测速仪对空间飞行微小物体的目标信号分辨,使得该测速系统最小可分辨φ0.5mm的飞行物体,其测量精度可控制在1.6%以内。     

ITER馈线系统虚拟设计

根据ITER馈线系统特点，采用模板剖建零件库，利用分层装配技术进行装配，提高了设计效率。通过有限元分析，及早发现设计问题，提高了馈线设计的合理性。     

铌三锡管内电缆导体交流损耗计算分析模型

为解决快变磁场中大电流和应变作用下,铌三锡(Nb3Sn)导体交流(Alternating Current,AC)损耗的模拟实验分析问题,本文进行了瞬变电磁场中宽应变区间的AC损耗计算技术探索,构建应变作用下的临界电流数学模型,把复杂变化场中基于应变的临界电流密度运用到磁滞损耗功率计算,对耦合损耗功率计算中的导体特征参数考虑应变效应,获得CICC导体AC损耗功率计算技术。在激发等离子体的快速励磁以及等离子体放电和破灭等情况下,由模拟对比分析发现应变作用算法的AC损耗功率更接近工程实际值;对比应变作用算法损耗功率和经典算法损耗功率的相对误差计算,其误差的变化小于15%。     

FE Stress Analysis of the Toroidal Field Magnets of HT-7U

1. IntroductionAs a full-superconducting tokomak, the HT－7Udevice is an advanced steady-state plamsa physicsdevice, which produces 3.5 T toroldal field (centralfield) at the plasma major radius of 1.7 m and about5.8 T peak field at the TF coils with the ripple of lessthan 1% within the range of plasma [11. The toroidalfield magnet system is one of the important parts ofHT-7U superconducting tokamak. This system consists of toroidal arrayed sixteen coils which spaced22.5' apart, and are sy…     

Research of the CICC Stability by the Numerical Code Gandalf

1. IntroductionIn this zpaper, we introduce cable--in-conduit conductor (i.e. CICC) which is used in the HT--7U superconducting TOkamak to obtain an effective andstable superconductor design for large magnets. Thedesign of the HT-7U superconducting TOkamak incorporates superconducting magnets of the toroidalfield (TF) and poloidal field (PF) systems [1]. TheCICC is cooled with a forced -flow supercritical helium at 4.5K. One of the most key problems relatedto conductor and coil prote…     

Electromagnetic Modeling of the Passive Stabilization Loop at EAST

A passive stabilization loop (PSL) has been designed and manufactured in order to enhance the control of vertical instability and accommodate the new stage for high-performance plasma at EAST.Eddy currents are induced by vertical displacement events (VDEs) and disrup-tion,which can produce a magnetic field to control the vertical instability of the plasma in a short timescale.A finite element model is created and meshed using ANSYS software.Based on the simulation of plasma VDEs and disruption,the distribution and decay curve of the eddy currents on the PSL are obtained.The largest eddy current is 200kA and the stress is 68MPa at the outer current bridge,which is the weakest point of the PSL because of the eddy currents and the magnetic fields.The analysis results provide the supporting data for the structural design.