低混杂波电流驱升与等离子体平衡

本文研究了低混杂波电流驱动与等离子体平衡问题．考虑了感应电场，得到了自洽方程组，并把它应用于托卡马克工程实验混合堆电流驱升阶段的某一时刻，研究了该时刻低混杂波电流驱动与ＭＨＤ平衡。计算中采用了一个较宽的波谱，得到了电流与安全因子ｑ的分布。     

EAST低混杂波功率沉积和电流驱动剖面控制的数值模拟

对原有的低混杂波电流驱动模拟程序进行改进,使之能够研究EAST上如何控制低混杂波功率沉积和电流驱动分布.在EAST非圆截面的平衡位形下,应用改进后的程序详细计算不同低混杂波功率谱、等离子体密度和温度分布对低混杂波功率沉积位置和电流驱动剖面分布的影响.通过计算发现,选取合适的低混杂波功率谱,等离子体温度分布和密度分布可以对功率沉积位置和电流驱动分布的剖面进行控制;调节等离子体温度分布可以很好的控制低混杂波近轴电流驱动分布和离轴电流驱动分布.     

低混杂波电流驱动下注入杂质的输运

在欧姆放电和低混杂波电流驱动条件下,应用激光吹气技术注入金属杂质,用真空紫外谱仪测量了杂质线的辐射,给出了ＨＬ－１Ｍ 装置欧姆等离子体和低混杂波电流驱动等离子体杂质输运的研究结果。用杂质输运程序ＬＢＯ进行数值模拟,得出了等离子体中杂质的扩散系数Ｄ（ｒ） 和对流速度ｖ（ｒ）。在低混杂波电流驱动条件下,等离子体杂质的输运系数相对欧姆放电等离子体杂质的输运系数减小了５０％ 左右。结果表明,在ＨＬ－１Ｍ 装置上低混杂波电流驱动等离子体相对通常欧姆等离子体杂质的约束性能明显得到了改善     

HT-7托卡马克大功率低混杂波电流驱动的实验研究

在HT-7超导托卡马克成功进行了大功率（P_LHW=100—800 kW,f=2.45 GHz）低混杂波电流驱动实验.研究了不同入射功率和等离子体密度下的低混杂波电流驱动效率.获得了以平均电子密度增加、氘阿尔法（D_α）线辐射减少为特征的粒子约束改善;粒子约束时间τ_p增加了约1.5倍.仔细研究了能量约束时间与等离子体密度和低混杂波功率的关系. 关键词： 托卡马克 低混杂波 约束改善 电流驱动效率     

低混杂电流驱动实验中高能电子的回旋辐射谱分析

在低混杂电流驱动实验中，研究由波驱动的快电子的行为对理解低混杂波驱动物理是十分重要的。     

托卡马克低混杂波电流驱动实验中低混杂波传播的解析分析

通过对小参量δ=(ω²_pe/ω²)^-1展开,导 出了简化但普遍的低混杂波电流驱动(LHCD)参量状态下的低混杂波色散方程.讨论了环形效 应(环向磁场的R^-1关系及磁面的Shafranov位移)引起的平行折射率的上移或下 移及慢波与快波的模转换条件,得到一个关于低混杂波可以向等离子体内部传播的充分条件 ,它与LHCD实验中普遍观察到的密度极限现象有密切联系.预期的临界密度n_ec 关键词： 托卡马克 低混杂波电流驱动 密度极限     

随机介质层对低混杂波传播的影响

本文采用随机模型,讨论等离子体边界层密度涨落对低混杂波的散射。色散关系中考虑了电磁项及E×B对流项。结果表明:考虑电磁效应之后,低混杂波的透射率(透过密度涨落层进入等离子体中心区的波强度与入射波强之比)减小,而反射率增加。 关键词：     

HL—1M装置上低混杂波电流驱动实验研究

本文介绍了在ＨＬ－１Ｍ装置上进行的低混杂波电流驱动实验研究。     

托卡马克等离子体LHCD与ECCD的协同作用

本文通过求解Fokker-Planck方程和射线追踪技术,详细研究了托卡马克等离子体中,低混杂波电流驱动(LHCD)与电子回旋波电流驱动(ECCD)的协同作用,结果表明,这种协同作用有利于用EC波驱动电流;捕获电子效应对电流驱动有一定影响,特别是O波弱场注入时,影响更为明显;驱动的电流对平衡磁场很敏感,磁场的大小也影响驱动电流的剖面。     

一种新的航天器外露介质充电模型

为综合考虑高能电子辐射与周围等离子体对航天器外露介质充电的影响,在航天器内带电模型的基础上,通过添加边界充电电流来考虑等离子体与航天器介质表面的相互作用,并统一参考电位为等离子体零电位,建立了航天器外露介质充电模型,给出了新模型的一维稳态解法,并与表面充电模型和深层充电模型进行了对比分析.结果表明:新建模型能够综合考虑表面入射电流、深层沉积电流和传导电流对充电的耦合作用过程,实现外露介质表面和深层耦合充电计算,有利于全面评估航天器外露介质的充电问题.     

Experimental Studies on the Sustainment of Splieromak Plasmas by an Inductive Drive of the Toroidal Current

Sustainment of spheromak plasmas produced in an external equilibrium field has been demonstrated with a center current transformer (ohmic heating (OH) coil) which is used to inductively drive the toroidal current of the plasma. The OH coil is covered by a cylindrical metal liner. It provides the stability against the tilt and shift motions of spheromaks at the expense of the simple connection of its geometry. Since the spheromak is characterized by the elimination of external toroidal fields in association with nonconservation of a toroidal flux during magnetic relaxation, the metal liner was made electrically disconnected from the main vacuum vessel (spheromak mode). In the experiments, existense of the dynamo effect, meaning automatic generation of toroidal flux similar to that of a reversed field pinch (RFP), is observed. Measured MHD activity consists of multihelicity helical modes with toroidal mode numbers N = 1-3. In order to investigate the difference between spheromaks and RFP's in the MHD activity during sustainment, experiments have also been made with the metal liner of the OH coil connected with the vessel (RFP mode). The dynamics of the MHD activities observed are compared with those obtained from the three-dimensional MHD simulations by Katayama and Katsurai [18], and their implication in the dynamo effect is discussed.     

托卡马克等离子体电流爬升阶段逃逸电子行为

 分析了电流爬升阶段等离子体密度和电流爬升率对逃逸电子行为的影响,研究了低杂波辅助电流驱动条件下的逃逸电子辐射行为。结果发现：电流爬升阶段等离子体密度的大小严重影响了电流爬升阶段甚至电流平顶阶段逃逸电子的行为,较低的等离子体密度将会导致放电过程中比较强的逃逸电子辐射;低能逃逸电子辐射随着电流爬升率的增大而增强;低杂波辅助电流爬升可以有效地节约装置的伏秒数;降低放电过程中的环电压,可有效抑制逃逸电子的产生。     

On confinement characteristics of the newly developed sawtooth-free plasmas in KSTAR tokamak

Development of advanced scenarios, an important experimental goal of the Korea superconducting tokamak advanced research (KSTAR) project, has just begun. The safety factor (q) profile is a key to achieve these advanced scenarios. Particularly the hybrid scenario, one of the advanced scenarios, can be established generally with low magnetic shear (s) at the center with central q-value above unity so to avoid sawtooth instability. This q-profile was successfully produced using early divertor formation during a plasma current ramp-up phase in KSTAR. Auxiliary heating was also employed during the current ramp-up phase to delay the inductive current diffusion to the center of the plasma. In addition to the early divertor formation method, the target q-profile was attempted to be achieved by modifying the plasma current waveform using the so-called, ‘current-overshoot’ method and the timing of L-mode to H-mode transition. In this work, the confinement characteristics of these sawtooth-free regimes are investigated. The global energy confinement time is calculated and compared with that of conventional H-modes in KSTAR. The confinement enhancement factor reveals that the newly developed discharges are not improved over H-modes contrary to results of other tokamaks. To investigate the reason, transport modeling is performed self-consistently with an integrated simulation package incorporating plasma equilibrium, transport, and heating and current drive. The current ramp-up phase is simulated and impact of early divertor formation, current-overshoot, and early L–H transition on the target q-profile and s/q profile is addressed. The s/q profile is found to be not improved in these discharges compared with hybrid scenarios reported in other tokamaks. Based on these results, future experimental directions are addressed to access the hybrid regimes in KSTAR.     

HL-2A极向场线圈系统的优化设计

通过对原ＡＳＤＥＸ极向场线圈系统进行改造,优化设计出ＨＬ－２Ａ极向场线圈系统,模拟计算了磁场位形演化并估算了伏秒消耗。改造后的极向场线圈系统能够形成８００ｋＡ的等离子体电流,并能产生拉长截面的等离子体偏滤器的位形。分析了改造后的极向场线圈系统的电磁特征,计算了单零,双零及Ｄ形限制器三种等离子体平衡位形。     

AC loss in a high-temperature superconducting coil

In a typical superconducting coil made of BSCCO/Ag tape, both amplitude and direction of the magnetic field determine the critical current, resistive voltage and AC loss. The distribution of the magnetic field along and across the superconducting tape in a coil is rather complex. This gives rise to the question: how accurate can one predict the critical current, V–I characteristic and AC loss of the AC coil from results of short sample measurements? To answer this question, we have measured and compared the characteristics of a short sample and a small coil employing 14 m of the same tape at 77 K. The comparison is performed as follows. First, a short sample is characterised with regard to the field dependence of the critical current, V–I characteristic and the AC loss. Second, the distribution of the magnetic field along the tape in a coil is accurately calculated. From the data, the voltage along the tape and the loss of the tape in the coil are found. Finally, the resistive voltage and the AC loss of the complete coil are calculated and compared to measured AC losses in the frequency range of 0 to 160 Hz, typical for power applications.     

Induced current of high temperature superconducting loops by combination of exciting coil and thermal switch

With its commercialization, the second-generation (2G) high temperature superconducting (HTS) RE—Ba—Cu—O (REBCO, RE is rare earth) tape is extensively applied to the superconducting magnets in the high magnetic fields. However, unlike low temperature superconducting (LTS) magnets, the HTS magnet cannot operate in the persistent current mode (PCM) due to the immature superconducting soldering technique. In this paper, an exciting method for two HTS sub-loops, so-called charging and load loops, is proposed by flux pump consisting of exciting coil and controllable thermal switch. Two HTS sub-loops are made of an REBCO tape with two slits. An exciting coil with iron core is located in one sub-loop and is supplied with a triangular waveform current so that magnetic field is generated in another sub-loop. The influence of magnetic flux on induced current in load loop is presented and verified in experiment at 77 K. The relationship between the induced magnetic flux density and the current on the sub-loops having been calibrated, magnetic flux density, and induced current are obtained. The results show that the HTS sub-loops can be excited by a coil with thermal switch and the induced current increases with magnetic flux of exciting coil increasing, which is promising for persistent current operation mode of HTS magnets.     

跑道型Bi系高温超导双饼线圈I～E特性计算与实验研究

本文使用Ansys有限元分析软件,建立三维跑道线圈模型,考虑超导线截面电流密度的非均匀分布特性,计算Bi系高温超导双饼线圈中各区域磁场分布、临界电流分布、电流密度分布和电场分布,从而计算线圈的I～E关系曲线,为超导线圈提供一个更为准确的检验标准,对照线圈的测试结果,用此程序计算的线圈I～E关系曲线与测试曲线吻合的较好.     

Rogowski线圈信号电阻对纳秒级脉冲大电流的响应

 研制了一种自积分型Rogowski线圈,从电路理论和电路仿真角度分析了信号电阻的寄生电感和线圈对地电容对测量信号的影响。采用电阻并联的方法,制作了小电感信号电阻。在定标和大电流测量实验中,小电感信号电阻的使用,消除了测量信号的平顶振荡和波形畸变,验证了理论分析的正确性。经定标,采用小电感信号电阻的Rogowski线圈对方波脉冲前沿的响应为11 ns,灵敏度为4.25 mV·A-1。该线圈性能稳定,已用于测量长脉冲强流电子束加速器二极管的电流,测得的电流波型平顶较好,半高脉宽为180 ns,幅度约为15.36 kA。     

Formation of advanced tokamak plasmas without the use of an ohmic-heating solenoid

A new operational scenario of advanced tokamak formation was demonstrated in the JT-60U tokamak. This was accomplished by electron cyclotron and lower hybrid waves, neutral beam injection, and the loop voltage supplied by the vertical field and shaping coils. The Ohmic heating (OH) solenoid was not used but a small inboard coil (part of the shaping coil), providing less than 20% of total poloidal flux, was used. The plasma thus obtained had both internal and edge transport barriers, with an energy confinement time of 1.6 times H-mode scaling, a poloidal beta of 3.6, and a normalized beta of 1.6, and a large bootstrap current fraction (>90%). This result opens up a possibility to reduce, and eventually eliminate, the OH solenoid from a tokamak reactor, which will greatly improve its economic competitiveness.     

MgB2超导线圈的交流损耗仿真和实验研究

本文采用MgB2／Fe/Cu单芯复合线材制作了一个小型实验线圈，并以此为基础，对用MgB2线、带材制成的线圈在承载较大电流情况下的交流损耗特性进行了仿真和实验研究，结果表明，为使MgB2／Fe／Cu复合线材适于电力应用，应设法大幅降低基体损耗．