利用扫描电镜研究三维电极主电极表面腐蚀状况

借助扫描电镜（SEM）对不同实验条件下的三维电极主电极表面腐蚀状况进行研究。结果表明，三维电极主极阳极的内侧腐蚀程度远大于其外侧，水样性质、电极材料性质对电极的腐蚀程度有很大的影响，不锈钢做三维电极主电极优于铝、铁电极。为三维电极主电极的选材提供了一定的理论依据。     

R－X图解法计算多级串联理想混合反应器

论述Ｒ－Ｘ图解法计算多级串联理想混合反应器的基本原理，并结合实例，对Ｒ－Ｘ法的计算步骤予以详细介绍，为多级串联反应器的设计与计算，提供一种新颖适用的图解计算方法。     

Analysis of low load transients for the Vandellòs-II NPP: Application to operation and control support

The Technical University of Catalonia (UPC) has been jointly working with the Asociación Nuclear Ascó-Vandellòs (ANAV) for a number of years in order to establish, qualify and use best estimate (BE) models for the reactors under the control of ANAV. ANAV is the consortium that is responsible for operation of the Ascó and Vandellòs-II reactors. The reactors are Westinghouse-design three-loop PWRs with an approximate electrical power of 1000 MW. The existing integral plant models for each plant are currently used for many different purposes among which are support of plant operation and control. Quite a number of studies have been done in order to improve both safety and plant competitiveness. Most of these dynamic analyses were carried out in relation to transients starting at nominal full power or at least, very close to full power. This paper develops a specific use of the Vandellòs-II plant model for operation and control support at low power involving new ranges of system actuation parameters. It also examines scenarios that are somewhat different from those typically analysed. The study starts showing the results of an assessment case, which is a start-up test and provides some additional qualification, and subsequently attempts to establish calculations to support both an improvement in feed water controls and to set up operating recommendations for low-load manual operation of feed water turbo-pump. Both results hopefully, will produce an outcome, which leads to an improvement in safety and reduces reactor trip probability.     

灯泡贯流泵装置的基本流态分析

为了回答灯泡贯流泵装置中的灯泡体究竟应该前置还是应该后置的问题,应用水泵装置三维湍流数值模拟的方法分别研究了南水北调东线工程某泵站前置灯泡和后置灯泡贯流泵装置两个不同方案的流态,揭示了前置灯泡和后置灯泡贯流泵装置的基本流动属性;数值模拟的结果得到流道模型试验的验证。研究结果表明:前置灯泡贯流泵装置的进、出水流态均匀平顺,水力损失较小;后置灯泡贯流泵装置的进水流态均匀平顺,但出水流道内存在明显的偏流和旋涡流动,水力损失较大;灯泡体前置符合水力学的基本原理,是获得最佳灯泡贯流泵装置水力性能的必要条件之一。     

我国核裂变能可持续发展战略研究

本文从科学技术的角度,分析我国国民经济增长对核能发展的需求,探讨我国核能的近中期发展战略构想,指出为实现其发展战略目标而应重点研究的关键科学技术与问题,并提出一些相关的政策建议,为国家制定核能中长期发展规划提供参考。     

中空纤维酶膜反应器及其动力学初步探讨──Ⅰ．单酶系统中空纤维酶膜反应器

单酶系统中空纤维酶膜反应器是用天津纺织工学院研制的ＴＦＣ－００３型聚砜中空纤维超滤器固定β－淀粉酶，在一定条件下催化可溶性淀粉制取麦芽糖的反应器。试验中，对温度、ｐＨ、酶及底物浓度变化动力学参数进行了初步探讨，试验重复性好。     

SIMULATION OF MICROMIXING IN A TURBULENT TUBULAR REACTOR WITH CONCENTRIC FEED

Turbulence on the axis of a pipe is isotropic and homogeneous and the rate of turbulent energy dissipation, ε, is known as a function of the velocity, pipe diameter and viscosity. When, however, a concentric feed pipe is introduced (as in a reactor), the ε field does not seem to be known. Evidence from fast, mixing-controlled reactions indicates a disturbance near to and downstream from the feed pipe with an increase in ε. Because of the lack of experimental information, the radial and axial distribution of ε has been modeled. One parameter—ε at the outlet of the feedpipe—is undetermined in this model. It is shown how the radial dispersion and especially the micromixing and reaction of fluid emerging isokinetically from the feed pipe can then be calculated, using a one-dimensional, radially averaged formulation. An application to four coupled, mixing-controlled reactions is included. Simulated and measured product distributions compared satisfactorily at various concentration levels and two solution viscosities. Whereas the new model is plausible, more work is needed to understand how a feed pipe modifies the flow in its vicinity.     

德国艾柯夫SL-500采煤机变频器故障及分析

晋城煤业集团引进德国艾柯夫SL-500采煤机,在使用过程中,短时间内连续出现多台变频器烧坏现象,这在艾柯夫采煤机使用过程中是从未有过的事,也给本公司的原煤生产造成了很大影响。为了杜绝此类事情的再次发生,特对本次的故障排除方法进行了认真的分析总结,为今后应用与修理采煤机提供了意见。     

T型薄壁管节点应力集中系数有限元分析

通过有限元的方法,分析了T型薄壁管节点受平面内弯矩作用下的疲劳行为,得到了应力最大值的位置和拟合出用于预测T型薄壁管节点受平面内弯矩作用下的应力集中系数的参数公式。     

Theoretical investigation on the steady-state natural circulation characteristics of a new type of pressurized water reactor

1 Introduction With respect to the inherent safety of nuclear re- actors, application of passive systems/components including natural circulation phenomena as the main mechanism is intended to simplify the safety-related systems and to improve their reliability, to reduce the effect of human errors and equipment failures, and to provide more time to enable the operators to prevent or mitigate serious accidents. Natural circulation is the main mode of heat removal for removing decay heat from t…