Properties of intermediate-frequency vacuum arc in sinusoidal curved contact and butt contact

In this report,two new contact structures of a vacuum interrupter with a sinusoidal curved surface are proposed to improve the capability by increasing the surface area.The experimental investigation of vacuum arc at intermediate frequency(360-800 Hz)was conducted and the results were compared with a butt contact with the same contact diameter(41 mm)and the same material.By analyzing the arc behavior,arc voltage characteristics,arc energy,current interrupting capacity,ablation of the anode contact and condensation of the arc products at a 3 mm gap,the differences in their vacuum arc characteristics were determined.The correlations of their arc energy with the amplitude and the frequency of the current were also achieved.Analysis suggests that the ruled curved contact has strong application potentiality because of its low arc energy,low arc voltage noise and arc voltage peak,light ablation on the surface of the anode contact and high interrupting capacity.     

不断变化、充满挑战的景象

无论在贫国还是在富国,能源问题都是一个快速上升的政治问题。油价已超过100美元一桶。全球变暖归因到煤及其他化石燃料。生物燃料受到更加密切的关注,包括对粮食生产和供应的影响。核能再一次接受人们的辩论。     

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民意测验表明,与几年前相比,英国公众离接受新建核电站更近了。然而,这种支持依然很脆弱。核能在英国的声望在21世纪的头几年和现在有了很大的提高,除了顽固反对核能的少数派外,公众普遍接受新建核电站,以迎接能源安全和气候变化的双重挑战,但是新建核电站的这种必要性要以合适的方式向公众提出。核工业一路走     

重离子径迹模板中组装半导体CdS一维纳米材料

用重离子辐照的聚碳酸酯为模板,采用电化学沉积法制备了半导体CdS纳米线和纳米管.通过选用不同蚀刻时间的模板,得到了直径20～100 nm、长度20～30 μm范围、粗细均匀且具有纤维锌矿结构的CdS纳米线与纳米管.利用扫描电子显微镜(SEM)、X射线衍射(XRD)和透射电子显微镜(TEM)对CdS纳米线与管的形貌和晶体结构特征进行了表征.     

Nuclear Fusion Within Extremely Dense Plasma Enhanced by Quantum Particle Waves

Quantum effects play an enhancement role in p-p chain reactions occurring within stars.Such an enhancement is quantified by a wave penetration factor that is proportional to the density of the participating fuel particles.This leads to an innovative theory for dense plasma,and its result shows good agreement with independent data derived from the solar energy output.An analysis of the first Z-pinch machine in mankind’s history exhibiting neutron emission leads to a derived deuterium plasma beam density greater than that of water,with plasma velocities exceeding 10000 km/s.Fusion power could be achieved by the intersection of four such pinched plasma beams with powerful head-on collisions in their common focal region due to the beam and target enhanced reaction.     

西伯利亚化学联合体将集中俄罗斯所有的铀转化产能

正【俄罗斯西伯利亚化学联合体网站2014年1月20日报道】在2013年第二季度,安加尔斯克(Angarsk)电化学厂关闭了六氟化铀生产线,并将其生产线转到西伯利亚(Siberian)化学联合体。这样,西伯利亚化学联合体将成为俄罗斯最大的铀转化基地。之前有报道说,俄罗斯国家原子能集团公司(Rosatom)计划将西伯利亚化学联合体     

The Timing System of the Neutral Beam Injector on EAST

In order to synchronize the elements of the EAST Neutral Beam Injector(NBI)spatially located in several places,a distributed Timing System(TS) is developed in this paper.The timing system provides a clock reference for synchronization and an interlock protection of the EAST NBI system.It sends timing signals to field devices,controls the pulse widths of the timing sequences,and provides a sampling clock for the Data Acquisition System(DAS).The timing system also generates analog waveforms to control power supplies and gas supplies according to the operator’s configuration.The timing system is developed on a PXI(PCI extensions for Instrumentation) platform consisting of a Lab VIEW workstation and a timing control terminal.The timing control terminal consists of a timing node and several control interface crates.Two timing nodes are configured in one beam line.Each node is responsible for the timing sequence,analog generation and feedback control for one ion source.The architecture and implementation of the timing system are presented in this paper.     

Instructions for Manuscript Preparation

<正>Plasma Science and Technology(PST)is a journal reporting novel experimental and theoretical results and progress of interdisciplinary and application sciences in the fields related to Plasma Physics.Specific interested areas include:basic plasma phenomena;magnetically confined plasma;inertially confined plasma;astrophysics     

《核科学与工程》征稿简则

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Experimental Study of the Unsteady Actuation Effect on Induced Flow Characteristics in DBD Plasma Actuators

The main aim of this paper is to investigate unsteady actuation effects on the operation of dielectric barrier discharge(DBD) plasma actuators and to study induced flow characteristics of steady and unsteady actuators in quiescent air.The parameters affecting the operation of unsteady plasma actuators were experimentally measured and compared with the ones for steady actuators.The effects of excitation frequency and duty cycle on the induced flow pattern properties were studied by means of hot-wire anemometers,and the smoke visualization method was also used.It was observed that the current and the mean induced velocity linearly increase with increasing duty cycle while they are not sensitive to excitation frequency.Furthermore,with increasing excitation frequency,the magnitude of vortices shedding from the actuator decreases while their frequency increases.Nevertheless,when the excitation frequency grows beyond a certain level,the induced flow downstream of the actuator behaves as a steady flow.However,the results for steady actuators show that by increasing the applied voltage and carrier frequency,the velocity of the induced flow first increases and then decreases with actuator saturation and the onset of the emission of streaky glow discharge.     

铅基快堆自然循环实验台架比例分析方法研究

铅基快堆具有良好的自然循环能力，研究其自然循环特性对提高反应堆固有安全性具有重要价值，而比例分析方法是建立合理可行铅基快堆自然循环实验台架的理论基础。本文通过无量纲化典型自然循环铅基快堆一回路系统的流体控制方程，确定主要的无量纲相似准则群；基于所构建的无量纲相似准则数对小型自然循环铅基快堆SNCLFR-10开展比例分析，获得双环路单相自然循环实验台架的几何和热工水力设计参数；对比分析额定工况下SNCLFR-10和缩比实验台架的关键热工水力参数，开展铅基快堆自然循环实验台架比例分析方法验证。研究结果表明，SNCLFR-10和缩比台架的关键热工参数模拟结果比值与理论推导比例关系吻合良好，建立的铅基快堆自然循环实验台架比例分析方法合理可行。      

自然循环铅基快堆一回路系统驱动力的关键影响因素研究

为深入研究影响自然循环铅基快堆一回路系统驱动力的关键因素,以自然循环铅基快堆SNCLFR-10为研究对象构建描述反应堆一回路自然循环稳态运行模型;从理论上量化分析冷/热池的热量传递、热源和热阱温度非线性分布、反应堆压力容器壁散热3种因素对自然循环能力的影响,并开展了相关数值模拟验证。结果表明,数值模拟结果与本研究理论计算值吻合较好;3种自然循环能力影响机制耦合作用将降低SNCLFR-10系统自然循环能力,导致自然循环流量与功率之间不再满足理论所得的1/3次方关系。      

Experimental validation of the TASS/SMR code for an integral type pressurized water reactor

The transient and setpoint simulation small and medium reactor (TASS/SMR) code has been applied to perform the safety analysis and performance evaluation of an integral type pressurized water reactor. Till now, the code has only been verified by using simplified and analytical problems as well as a reliable system code due to the lack of available experimental data. Recently, several kinds of experiments have been performed by focusing on an identification of the heat transfer characteristics at a heat sink and source, and the thermal hydraulic characteristics and the natural circulation performance in an integral effect test facility. In this paper, the TASS/SMR code has been validated by using the experimental data obtained from a separate effect test facility by focusing on the heat transfer characteristics and an integral effect test facility by focusing on the thermal hydraulic characteristics and the natural circulation performance. According to the validation results of the TASS/SMR code against the separate effect test and the integral effect test, the code predicts the overall variation of the thermal hydraulic parameters well, including the system pressure, fluid temperature, mass flow rate, etc., and it is applicable for the safety analysis and performance evaluation of an integral type pressurized water reactor.     

Experimental investigation of natural circulation instability in a BWR-type small modular reactor

The Purdue NMR (Novel Modular Reactor) represents a BWR-type small modular reactor with a significantly reduced reactor pressure vessel (RPV). Specifically, the NMR is one third the height and area of a conventional BWR RPV with an electrical output of 50 MWe. Experiments are performed in a well-scaled test facility to investigate the thermal hydraulic flow instabilities during the startup transients for the NMR. The scaling analysis for the design of natural circulation test facility uses a three-level scaling methodology. Scaling criteria are derived from non-dimensional field and constitutive equations. Important thermal hydraulic parameters, e.g. system pressure, inlet coolant flow velocity and local void fraction, are analyzed for slow and fast normal startup transients. Flashing instability and density wave oscillation are the main flow instabilities observed when system pressure is below 0.5 MPa. And the flashing instability and density wave oscillation show different type of oscillations in void fraction profile. Finally, the pressurized startup procedure is recommended and tested in current research to effectively eliminate the flow instabilities during the NMR startup transients.     

小型自然循环铅基快堆内部始发事件选取研究

始发事件是铅基反应堆确定论安全分析和概率安全评价的起点和基础,对反应堆优化设计和安全运行具有重要指导作用。本文基于小型自然循环铅基快堆SNCLFR-100当前的设计方案,参考其他先进快堆始发事件选取经验,以广义“堆芯熔化”作为顶层目标事件,采用主逻辑图（MLD）方法推导其内部始发事件,最后得到一组较完整的内部始发事件清单。本文研究可为自然循环铅基快堆安全分析工作的开展提供理论依据。      

基于CFD的池式快堆多物理耦合分析方法研究

基于临界/次临界点堆中子动力学模型、燃料棒传热模型、热交换器和多孔介质等辅助热工水力模型,采用显式迭代和动态链接库技术（DLL）,利用商用计算流体力学（CFD）程序FLUENT的用户自定义函数（UDF）实现中子动力学、燃料棒热传导等和快堆堆池冷却剂流动换热的耦合计算,开发池式快堆多物理耦合计算程序CFD/PF。采用CFD/PF开展小型自然循环铅铋快堆SNCLFR-10无保护超功率事故（UTOP）模拟,并与国际知名快堆多物理耦合分析程序SIMMR-III的计算结果开展Code-to-Code对比分析。研究结果表明:CFD/PF与SIMMER-III的分析结果吻合良好,耦合程序的开发取得了初步成功,可用于分析池式快堆堆池内的复杂三维流动和换热现象。      

基于CFD的池式快堆多物理耦合分析方法研究

Based on the critical/subcritical point kinetics model, the fuel pin heat transfer model, and the auxiliary thermal hydraulic models such as the heat exchanger model and the porous media model, a multi-physical coupling code CFD/PF was developed by means of the explicit iteration method, dynamic link library technique (DLL) and user-defined functions (UDF) of FLUENT. The CFD/PF was used to carry out the simulation of SNCLFR-100 unprotected transient of over power (UTOP) of a small natural circulation LBE cooled fast reactor, and the code-to-code comparison analysis was conducted with the renowned multi-physical coupling code SIMMER-III. The results indicated that the CFD/PF simulation results are in a good agreement with SIMMER-III calculation results, and the multi-physical analysis method and code development have been achieved initial success, which can be used to analyze the complex three-dimensional flow and heat transfer phenomena in pool-type fast reactors.     

一维自然循环比例分析的结果与讨论

根据一维自然循环比例分析理论模型推导的试验装置与实际电站热工水力特性的相似准则,对整体性能试验装置主要参数的确定方法进行了深入讨论。结果表明:采用小尺度、等压力、同工质的实验装置模拟实际系统自然循环现象更为准确实际,单相和两相自然循环比例准则可同时满足,不存在复杂比例变化带来的失真,不利因素是试验成本偏高。同工质非等物性(不等压)模拟能够降低试验成本,但比例参数不能满足从单相自然循环到两相自然循环的平滑过渡。如保持功率连续,其速度比和特征时间比会有所差异。     

基于修改后RELAP5/MOD3.2的氟盐高温堆实验回路分析

大型热工流体整体效应系统实验(CIET)台架是为模拟氟盐冷却高温堆(FHR)热工水力响应而设计的实验回路,采用DOWTHERM A模拟氟盐作为冷却剂。通过在RELAP5/MOD3.2程序中加入DOWTHERM A物性参数以及传热关系式,计算FHR实验回路CIET在两种工况下的热工水力行为,并与实验结果进行对比,计算工况包括强迫循环条件与自然循环条件。计算结果表明:在强迫循环条件下,堆芯热量主要靠盘管式空气换热器(CTAH)排出,堆芯进出口冷却剂温度及CTAH出口冷却剂温度与实验值符合良好,CTAH进口冷却剂温度与实验值有些微偏差;在自然循环工况中,堆芯热量主要通过DHX与堆芯辅助冷却系统(DRACS)回路的换热带走,DHX及DRACS的流量与实验值接近,相对误差在10%左右,验证了修正后RELAP5/MOD3.2的正确性。     

一维自然循环比例分析的理论模型

整体性能试验研究是验证先进非能动压水堆核电站堆芯冷却系统设计有效性的核心技术,一回路系统两相自然循环热工水力特性比例分析是确定整体性能试验装置尺度的主要理论依据。以一维漂移流模型为基础,对整个一回路两相自然循环系统控制方程积分,并求得稳态解,由此获得了系统的流动条件。应用初始流动条件与边界条件,对两相自然循环系统控制方程直接无量纲化,最终得到了整体性能试验装置与实际非能动电站热工水力特性的相似准则。