挤压式旋转切割弹丸注入器

阐述了合肥弹丸注入器的工作原理，结构特点及液氮冷冻下ＣＨ４弹丸的制造和发射实验。结果表明，该注入器可产生Φ１ｍｍ×１ｍｍ、速度约４５０ｍ／ｓ的弹丸，离散度小于±０．３，弹丸重复性及完整性较好。     

Matlab、Access和VB.NET混合编程方法的研究和应用

在等离子体单粒子模拟程序开发中,需要进行大量的模拟运算,保存和分析大量的模拟结果.Matlab是科学和工程计算的常用工具,但不具备大量数据的管理能力.Microsoft Access是广泛应用的数据库管理和应用软件,VB.NET是功能强大,简单易学的程序设计语言工具.结合这3种软件最新版本的新特性,通过三者的混合编程,在VB.NET中利用ActiveX技术实现对Matlab的调用,使用Matlab进行模拟运算,并将模拟结果保存到Access数据库中,利用三者各自的优点,编写出了适合需要的应用程序.     

Matlab与VB．NET混合编程中数据存储方式的研究

在Matlab与VB.NET的混合编程中,Matlab计算结果的存储是一个非常关键的问题.通过VB.NET直接调用Matlab的相关函数无法实现存储功能.介绍了在VB.NET与Matlab的混合编程中,使用StreamWriter类的write和writeline方法将数据写入txt文本文件,使用ActiveX自动化服务将结果保存为xls文件的两种方法,比较了二者各自的特点,并指出了开发过程中应注意的问题.     

SUNIST球形托卡马克的研究进展

球形托卡马克为聚变能的商业应用提供了一条可能的途径。中国联合球形托卡马克SUNIST以真空室的环向和极向都有绝缘隔缝为结构特征。该装置的主要任务是研究低环径比等离子体的基本特性和等离子体的非感应加热与电流驱动。包括同轴磁螺旋性注入电流启动、电极放电辅助电子回旋波电流启动、电子伯恩斯坦波以及离子高次谐波快波加热与电流驱动。装置已经顺利组装完毕,并安装了磁测量、静电探针和软X射线等基本的诊断系统。目前正处于系统联调阶段。     

HT—7超导托卡马克第一壁He辉光硼化实验研究

为了降低聚变等离子体杂质的含量,改善等离子体性能,对HT-7进行了射频辅助的氦气直流辉光放电硼化.硼化后,等离子体参数提高,等离子体行为明显改善.由此证实了硼化为HT-7稳态运行提供了良好的壁条件.     

HT-7超导托卡马克第1壁B/C膜吸O性研究

通常在托卡马克第1壁沉积1层B膜,以降低托卡马克等离子体的O杂质。在HT-7第1壁位置处放了几个石墨样品,它们与HT-7一起硼化。硼化后取出部分样品膜,剩余样品留在真空室接受聚变等离子体的轰击。对鲜膜和轰击膜进行XPS分析,发现在成膜过程中B膜开始吸O;等离子体轰击时,B膜进一步吸O。O在膜中与B以化合态B2O3形式存在。并对实际中存在的一些问题进行了探讨。     

A Research Program of Spherical Tokamak in China

The mission of this program is to explore the spherical torus plasma with a SUNIST spherical tokamak. Main experiments in the start phase will be involved with breakdown and plasma current set-up with a mode of saving volt-second and without ohmic heating system, equilibrium and instability, current driving, heating and profile modification. The SUNIST is a university-scale conceptual spherical tokamak, with R = 0.3 m, A 1.3, Ip -50 kA, BT < 0.15 T, and PRF- 100 kW. The only peculiarity of SUNIST is that there is a toroidal insulating break along the outer wall of vacuum vessel. The expected that advantages of this arrangement are helpful not only for saving flux swing, but also for having a deep understanding of what will influence the discharge startup and globe performances of plasma under different conditions of strong vessel eddy and ECR power assistance. Of course, the vessel structure of cross seal will be at a great risk of controlling vacuum quality, although we have achieved positive results on sim     

Identification of Plasma Boundary and Position for HL-2A Tokamak

Using the virtual-case principle, the plasma boundary, the plasma current center, and the x-point are identified for the HL-2A tokamak. The plasma current is represented by the current center and the virtual multipole moments which produce a magnetic flux in a form of polynomial. Adaptive parameters in the polynomial are determined by the least-square fit of the poloidal magnetic fields. The measurement of the magnetic field is performed using pick-up coils. The virtual-case principle is applied outside the plasma boundary. The virtual-case currents decide the position of the current center and produce a negative confinement magnetic field inside the plasma and the magnetic field generated by the plasma current outside the plasma boundary. The convergence is fast enough to get a picture between the sequent shots. The configuration reconstructed is in good agreement with the TV image taken by camera with a tangential view.     

Coupling Effect between Equilibrium Field and Heating Field and Modification of the Power Supply System on SUNIST Spherical Tokamak

Strong inductive coupling between the heating field and equilibrium field is confirmed to be responsible for the poor plasma equilibrium in initial discharges on the SUNIST spherical tokamak. A modification project for the power supply system of equilibrium field coils is successfully performed to increase the duration time of plasma current flattop from nmch less than 1ms to about 2 ms.