接触网零件振动试验方法探讨

通过对接触网零件用紧固件的耐振动性能进行振后扭矩测试和横向振动采用压力环测试应变进行对比分析，提出了合理的接触网零件耐振动性能试验方法。     

某微型起爆器引起的一起误爆事故分析

该文分析某微型起爆器引起的一起误爆事故，指出该起爆器设计上的缺陷及其对作业安全的威胁，提出防患建议。     

煤矿许用毫秒延期电雷管研究

文中对影响煤矿许用毫秒延期电雷管沼气安全性与延期时间精度的因素进行了研究。应用正交设计研制了新的延期药配方，确定了合理的雷管结构及装配工艺参数，产品性能达到ＧＢ８０３１《工业电雷管》的规定。     

An experimental study on the pumping performance of molecular drag pumps

The pumping performance of molecular drag pumps (MDP) has been investigated experimentally. The experimented MDPs are a disk-type drag pump (DTDP), helical-type drag pump (HTDP) and compound drag pump (CDP), respectively. In the case of the DTDP, spiral channels of a rotor are cut on both upper surface and lower surface of a rotating disk, and the corresponding stator is a planar disk. In the case of the HTDP, the rotor has six rectangular grooves. The CDP consists with the DTDP, at lower part, and with the HTDP, at upper part. The experiments are performed in the outlet pressure range of 0.2–533 Pa. The inlet pressure and compression ratio are measured under the various conditions of outlet pressure and throughputs, and nitrogen is used for the test gas. At the outlet pressure of 0.2 Pa, the ultimate pressure has been reached to 1.0 × 10⁻² Pa for the HTDP, 1.3 × 10⁻⁴ Pa for the DTDP, and 3.6 × 10⁻⁵ Pa for the CDP. The maximum compression ratio of the CDP is much higher than those of the DTDP or HTDP. Consequently, the ultimate pressure of the CDP is the lowest one.     

Simulation of the VVER-1000 pump start-up experiment of the OECD V1000CT benchmark with CATHARE and TRAC-PF1

In the framework of joint effort between the Nuclear Energy Agency (NEA) of OECD, the United States Department of Energy (US DOE), and the Commissariat a l'Energie Atomique (CEA), France a coupled three-dimensional (3D) thermal-hydraulics/neutron kinetics benchmark for VVER-1000 was defined. The benchmark consists of calculation of a pump start-up experiment labelled V1000CT-1 (Phase 1), as well as a vessel mixing experiment and main steam line break (MSLB) transient labelled V1000CT-2 (Phase 2), respectively. The reference nuclear plant is Kozloduy-6 in Bulgaria. The overall objective is to assess computer codes used in the analysis of VVER-1000 reactivity transients. A specific objective is to assess the vessel mixing models used in system codes. Plant data are available for code validation consisting of one experiment of pump start-up (V1000CT-1) and one experiment of steam generator isolation (V1000CT-2). The validated codes can be used to calculate asymmetric MSLB transients involving similar mixing patterns. This paper summarizes a comparison of CATHARE and TRAC-PF1 system code results for V1000CT-1, Exercise 1, which is a full plant point kinetics simulation of a reactor coolant system (RCS) pump start-up experiment. The reference plant data include integral and sector average parameters. The comparison is made from the point of view of vessel mixing and full system simulation. CATHARE used a six-sector multiple 1D vessel thermal-hydraulic model with cross flows and TRAC used a six-sector, 18-channel coarse-mesh 3D vessel model. Good agreement in terms of integral parameters and inter-loop mixing is observed.     

浅谈小型水库安全管理现状及对策

济南市长清区小型水库运行管理中发现了一些值得探讨的问题.本文主要介绍了济南市长清区小型水库安全运行管理存在的主要问题,分析了问题产生的原因,提出了相应的处理对策,以供参考.     

Application of condition-based HRA method for a manual actuation of the safety features in a nuclear power Plant

A practical approach to develop a more realistic fault-tree model with a consideration of various conditions endured by a human operator is proposed. In safety-critical systems, the generation failure of an actuation signal is caused by the concurrent failures of the automated systems and an operator action. These two sources of safety signals are complicatedly correlated. The failures of sensors or automated systems will cause a lack of necessary information for a human operator and result in error-forcing contexts such as the loss of corresponding alarms and indications. It is well known that the error-forcing contexts largely affect the operator's performance. An automated system which consists of multiple processing channels and complex components is also affected by the availability of the sensors. This paper proposes a condition-based human reliability assessment (CBHRA) method in order to address these complicated conditions in a practical way. We apply the CBHRA method to the manual actuation of the safety features such as a reactor trip and auxiliary feedwater actuation in Korean Standard Nuclear Power Plants. Even the human error probability of each given condition is simply assumed, the application results prove that the CBHRA effectively accommodates the complicated error-forcing contexts into the fault trees.     

膜片式流量调节阀

介绍了用于油田开采工艺的膜片式流量调节阀的结构及其特点,分析了调节阀出口压力、进口压力对其流量的影响。受力分析和现场使用表明:该阀流量恒定精度(即恒流偏差)取决于膜片有效面积S与阀心下端有效面积S′之比,此值为12,其恒流比偏差为0·03,说明该阀的流量恒定精度高;该阀不易被杂质卡死,稀油中直径1mm的砂粒能顺利通过,而不影响阀的功能;膜片式流量调节阀是没有高加工精度要求的部件,普通车床即可生产,因此造价较低。     

美国食品安全管理法规与举措

以美国国会研究服务部对第107届国会就食品安全方面的一份报告为基础,主要对美国的公共健康问题现状、美国食品安全的联邦规范框架组成、美国食品安全控制最新进展和国会对食品安全提出的新议题做了综述,对我国的食品安全控制和管理体系的建设发挥一点借鉴作用。