液氮温区固-液复合绝缘气体小桥对沿面放电的影响

采用IEC脉冲电流法(IEC60270标准)对液氮温区超导复合绝缘沿面放电现象及其影响因素进行了研究。在六面屏蔽的局部放电实验室内,研究了不同放电条件对放电起始电压、放电量、击穿电压等的影响,进而研究了其作用机理,并用有限元方法开展了相关计算。实验数据表明,不同放电条件明显影响放电重复率、平均放电量、最大放电量等,放电产生的气泡越容易逸出,放电越严重;液氮的流动使放电起始电压有一定的升高,但对最终击穿电压影响不大;在放电通道上施加阻挡之后可明显提高最终的闪络击穿电压。     

Initial high beta operation of the HBT-EP Tokamak

HBT-EP is a new research tokamak designed and built to investigate passive and active feedback techniques to control MHD instabilities. In particular, HBT-EP will be able to test techniques to control fast MHD instabilities occurring at high Troyon-normalized beta, _N Ba/I_p [Tm/MA], since it is equipped with a thick, close-fitting, and adjustable conducting shell. The major goals of the initial operation of HBT-EP have been the achievement of high beta operation (_N 3) using only ohmic heating and the observation of MHD instabilities. By using a unique fast startup technique, we have successfully achieved these goals. A variety of MHD phenomena were observed during the high beta operation of HBT-EP. At modest beta (_N 2), discharges have been maintained for more than 10 msec, and these discharges exhibit saturated resistive instabilities. When _N approaches 3, major disruptions occur preceded by oscillating, growing precursors. During start-up, one or more minor disruptions are usually observed. A 1-D transport code has been used to simulate the evolution of the current profile, and these early minor instabilities are predicted to be double tearing modes. The simulation also reproduces the observed high beta operation when saturated neo-Alcator energy confinement scaling is assumed.     

The fusion-supported decentralized nuclear energy system

A decentralized nuclear energy system is proposed comprising mass-produced pressurized water reactors in the size range 10 to 300 MW (thermal), to be used for the production of process heat, space heat, and electricity in applications where petroleum and natural gas are presently used. Special attention is given to maximizing the refueling interval with no interim batch shuffling in order to minimize fuel transport, reactor downtime, and opportunity for fissile diversion. The smallest reactors could be deployed as nuclear batteries, kept in the equivalent of spent-fuel shipping casks and returned to nuclear fuel centers for refueling. These objectives demand a substantial fissile enrichment (7 to 15%). The preferred fissile fuel is U-233, which offers an order of magnitude savings in ore requirements (compared with U-235 fuel), and whose higher conversion ratio in thermal reactors serves to extend the period of useful reactivity and relieve demand on the fissile breeding plants (compared with Pu-239 fuel). Application of the neutral-beam-driven tokamak fusion-neutron source to a U-233 breeding pilot plant is examined. This scheme can be extended in part to a decentralized fusion energy system, wherein remotely located large fusion reactors supply excess tritium to a distributed system of relatively smallnonbreeding D-T reactors.     

Numerical analysis of magnetization AC losses in high-temperature superconducting slabs subjected to uniform strains

High-temperature superconductors in superconductor apparatuses are subjected to mechanical strains under operating conditions.These strains cause the degradation of the critical current densities and influence AC losses in the superconductors.Based on the dynamic process of thermomagnetic interaction,we report the results of numerical analysis of AC losses in an infinite high-temperature superconducting slab subjected to a uniform in-plane strain in an alternating external magnetic field parallel to the sample surface.The numerical analysis shows the details of electromagnetic phenomena in the slab and the dependences of AC loss on various external parameters including the uniform strain in the slab and the amplitude and frequency of the external magnetic field.In this paper,we find that whether the magnetic field fully penetrates the superconductor is the key factor that influences the features of AC loss.When the magnetic field cannot fully penetrate the superconductor,the loss rises with increasing strain or decreasing frequency.When the magnetic field can fully penetrate the superconductor,the feature is just opposite.We also analyze the effects of periodic strain on AC loss.It is interesting to find that when the periodic strain frequency equals the external magnetic field frequency,the AC loss reaches the maximum,regardless if the magnetic field fully penetrates the superconductor or not.     

Fuel provision for nonbreeding deuterium-tritium fusion reactors

Nontritium-breeding D-T reactors have decisive advantages in minimum size, unit cost, variety of applications, and ease of heat removal over reactors using any other fusion cycle, and significant advantages in environmental and safety characteristics over breeding D-T reactors. Considerations of relative energy production demonstrate that the most favorable source of tritium for a widely deployed system of nontritium-breeding D-T reactors is the very large (10 GW thermal) semicatalyzed-deuterium (SCD), or sub-SCD reactor, where none of the escaping³He (> 95%) or tritium (< 25%) is reinjected for burn-up. Feasibility of the ignited SCD tokamak reactor requires spatially averaged betas of 15 to 20% with a magnetic field at the TF coils of 12–13 T.On leave from Dept. of Electronic Engineering, University of Tokyo, Tokyo, Japan.     

The recombination of quasiparticles in x-ray superconducting tunnel detectors

The energy resolution of superconducting tunnel detectors is investigated from the point of view of the effect of recombination and boundary losses of nonequilibrium quasiparticles. Using the x-ray fluorescence method, the dependence of the signal on the energy of x-ray quanta is measured for Ti/Nb/Al/AlO_x/Al/Nb/NbN detectors. The form of the apparatus line is also investigated. The experimental data are analyzed using the diffusion model of tunnel detectors. __________ Translated from Izmeritel’naya Tekhnika, No. 8, pp. 59–64, August, 2006.     

应用于超导储能的双向DC/DC变换器的设计

以超导在电力系统中的应用为背景,超导储能方式具有更有效地提高电力系统稳定性和动态稳定性的优点,以满足超导储能应用的需要为目的,针对性地提出了一种新型应用于超导储能的隔离式的双向DC/DC变换器的电路拓扑结构。针对超导储能线圈的储能特性,设计了独特的双向充放电工作电路,有效保证了能量的双向流动,结合移相PWM技术,能够完全实现超导线圈的充放电功能。同时该变换器具有大功率、大电流、控制简单和全数字化等特点。该文详细地介绍和分析了主电路结构、工作原理和控制方法。根据上述理论设计出了相应的试验装置,并给出了实验结果,验证了应用于超导储能的双向DC/DC变换器的正确性。     

基于数字信号处理器与复杂可编程逻辑器件的三相电流源型超导储能不间断电源及其控制策略

该文介绍了一种基于DSP与CPLD的三相电流源型SMES-UPS装置,该装置在电网正常时可以用作超导纵场线圈(TFSC)的励磁电源,而在电网故障时又可以用作低温和真空系统的UPS电源。在电网正常时,通过对变流器交流侧有功、无功电流的控制不但可以保证超导线圈上电流按照设定速度上升到稳态值,而且可以保证变流器网侧的单位功率因素运行和低谐波污染;在电网故障时,通过分析负载电压和电流之间的定量关系,提出了基于负载电压反馈的交流侧电流实时控制策略,不但可以保证负载电压的幅值和频率稳定,还可以电压相位不随负载性质的变化而变化。文中还介绍了基于DSP与CPLD的SMES-UPS控制系统,该控制系统结构简单、可编程程度高。1 kVA的SMES-UPS样机实验结果表明文中所述的控制算法及其控制系统能够很好地实现SMES-UPS兼作EAST纵场励磁电源和低温、真空系统UPS电源的双重功能。     

超导磁体系统产生的磁场作用下的微重力环境

超导磁体系统产生的磁场力可抑制晶体生长过程中的自然对流,从而提高晶体结晶质量。通过理论分析,得到了实现微重力环境所要求的磁场强度分布。针对特定结构的超导磁体系统,数值模拟得到了不同晶体结晶过程中自然对流完全抑止所需要的线圈电流密度,以及工作空间内的磁场强度和磁加速度。以圆筒内水的自然对流为例,分别得到了重力作用下的流场和温度场,以及超导磁体系统微重力区内的流场和温度场。结果表明:通过特定的超导磁体结构和不同电流密度,可实现不同晶体结晶过程的微重力环境,达到抑止自然对流的目的。     

国际热核聚变实验堆磁体线圈终端盒的设计

线圈终端盒（CTB）是国际热核聚变实验堆超导磁体系统的重要组成部分，其内部组件的漏热常常是整个磁体系统的主要漏热源之一，在很大程度上决定着低温系统的液氦消耗量。本文从降低热负荷的角度对CTB内部冷屏、超导电流传输线、电流引线、阀及冷却管路、外部盒体的设计进行了详细阐述，为最终结构的确定提供了理论依据。