专用电子测试设备系统校准方法研究

介绍专用电子测试设备系统校准的方法，以及在实际工作中是如何实现专用电子测试设备系统静态，动态校准和如何编制校准软件实现自动校准。     

空空导弹地面检测设备校准方法研究

现阶段空空导弹地面检测设备仅能实现分单元单物理量参数的校准,为解决空空导弹产品综合参数校准需求,提出基于系统模拟空空导弹产品测试参数、模拟空空导弹产品电气测试接口、模拟空空导弹产品测试流程的校准方法,通过分析空空导弹产品参数及接口特征,设计公共基础校准测控平台和独立校准适配器,采用校准测控平台和校准适配器组合架构研制一套空空导弹地面检测设备校准系统,提升校准系统的通用性和扩展性,满足不同型号空空导弹产品参数的模拟校准。校准系统经现场验收测试,测试结果满足系统技术指标要求,校准系统已应用于空空导弹地面检测设备的现场原位校准,实现空空导弹产品综合参数校准。     

动力电池测试系统充放电电流校准的研究

动力电池测试系统是检测电池性能的主要设备。针对动力电池测试系统的校准,国内目前还未颁布相关的检定规程和校准规范,研究一种合理、方便、科学的校准方法非常必要。本文简单介绍了动力电池测试系统的计量特性,深入研究了动力电池测试系统充放电电流的校准方法和校准装置的选择,并对校准结果进行不确定度评定。     

电机出厂综合测试系统量值溯源的校准

旨在探讨电机出厂综合测试系统量值溯源校准的问题。在掌握电机出厂综合测试系统的结构、功能和原理的基础上,根据电机出厂检验所需的各项技术指标,选取合适的校准规范和标准设备,结合测试系统工作原理和各个参数的量值要求,详细阐述了此类测试系统的溯源校准的方法和量值校准点的选择,并介绍了测试系统在校准过程中量值纠偏的方法。提出的量值溯源的校准方式,能够解决此类电机出厂测试系统的量值溯源问题,满足生产企业的计量需求。     

航空专用测试设备整机校准工作探讨

正由于专用测试设备具有多参数、种类样式各一、集成化、体积大的特点,许多设备又没有设计计量接口,没有可借鉴的校准方法和校准设备,对标溯源困难,所以探索设计专用测试设备整机校准方法,对规范专用测试设备整机校准工作具有非常重要的现实意义。一、专用测试设备整机校准方法分类1.设计、加装计量接口,使用通用测量标准校准通用测试设备有标准的输入、输出接口,校准时     

专用测试系统校准技术探讨

测试系统是执行测试任务的传感器、仪器和设备的总称.专用测试系统量值控制和测量不确定度的控制对保证型号产品质量有十分重要的意义.专用测试系统校准方法的研究是国防军工计量的工作重点之一.本文针对专用测试系统的特点、现状、以及校准工作存在的问题,进行了分析研究.对专用测试系统的校准方法及测量不确定度评定进行了适当的探讨.     

直升机旋翼锥体和动平衡测量仪校准方法研究

直升机旋翼锥体及动平衡测量系统是直升机专用测试设备。本文介绍了自行研制的这种设备的校准装置原理和校准方法。     

专用测试设备校准探讨

与军工产品科研生产密切相关的专用测试设备的校准,是军工产品质量保证的关键因素,越 来越受到生产研制和使用方的重视.不断完善专用测试设备的校准方法,使之更科学、更规范,是计量部门一直致力研究的问题.本文介绍了专用测试设备的特点、现状、专用测试设备现场校准及自动校准的必要性和特殊性,对专用测试设备的校准方法及不确定度评定等作了论述,并展望了专用测试设备校准的发展方向.     

一种模拟舱综合测试系统校准方法

专用测试设备的校准是保证武器装备技术指标准确可靠的重要手段,是计量从业人员永久面临的课题。由于缺少专门的校准规程(规范)指导,随着装备系统高度信息化、复杂化的快速发展,给校准工作带来了诸多不便。模拟舱综合测试系统作为一种专用测试设备,如何开展计量校准工作,本文通过对模拟舱综合测试系统结构原理、计量特性等因素的分析,提出模拟舱综合测试系统校准方法。     

专用测试设备校准方法的实践

文章针对专用测试设备校准工作中遇到的问题,基于专用测试设备的特点,分别介绍了专用测试设备校准点的选取、校准参数的分类及校准方法,同时阐述了校准规范的编写和管理要求.     

民机变频交流电源供电特性测试系统校准技术研究

概述了民用飞机电源系统发展趋势,针对变频交流电源系统,结合国内外研究现状,阐述了民机变频交流电源供电特性测试系统校准技术研究的意义。依据变频交流电源供电特性测试系统的技术要求,研究了校准方法并编写了校准规范;基于直接数字频率合成（DDFS）、直接数字波形合成（DDWS）、宽带信号放大和滤波等技术,研制了变频交流电源供电特性校准信号源;依据校准方法中的工作流程及信号设置,编制了校准程序,形成了自动化的校准系统。最后,将上述校准系统应用于多个主机厂、所的电源试验系统,完成了现场试验验证。通过上述研究过程,建立了完善的民机电源供电特性测试系统校准能力,为未来民机电网特性和用电设备供电适应性领域的研究奠定了坚实基础。     

功率吸收钳校准的不确定度分析

功率吸收钳是测量受试设备电源线上辐射骚扰功率的重要设备，在电子和电气设备的电磁兼容性检测领域有着广泛的用途。功率吸收钳插人损耗的准确与否以及校准结果的不确定度与测量结果密切相关。作经过对吸收钳校准方法的分析，探讨了对校准结果不确定度有影响的各个因素，建立了评定校准结果不确定度的数学模型。中对校准结果的不确定度评定方法作了简要介绍。     

An analysis of safety-critical digital systems for risk-informed design

This paper quantitatively presents the results of a case study which examines the fault tree analysis framework of the safety of digital systems. The case study is performed for the digital reactor protection system of nuclear power plants. The broader usage of digital equipment in nuclear power plants gives rise to the need for assessing safety and reliability because it plays an important role in proving the safety of a designed system in the nuclear industry. We quantitatively explain the relationship between the important characteristics of digital systems and the PSA result using mathematical expressions. We also demonstrate the effect of critical factors on the system safety by sensitivity study and the result which is quantified using the fault tree method shows that some factors remarkably affect the system safety. They are the common cause failure, the coverage of fault tolerant mechanisms and software failure probability.     

三相不平衡度测量仪校准方法的研究

测量电网中的三相不平衡度是保障电力系统安全可靠运行的重要前提,现在测量三相不平衡度的仪器越来越多,采用的结构原理也各不相同,质量参差不齐。如何校准这些仪器目前还没有统一的方法,该文介绍一种对三相不平衡度测量仪进行校准的方法,为其溯源提供了方便。     

Risk analysis of surveillance requirements including their adverse effects

Technical specifications for nuclear power plants require periodic surveillance testing of the standby systems important to safety. This regulatory requirement is imposed to assure that the systems will start and perform their intended functions in the event of plant abnormality. However, operating experience suggests that, in addition to the beneficial effects of detecting latent faults, the tests may have adverse effects on the plant's operation or equipment. This paper defines those adverse effects of testing from a risk perspective, and then presents a method to quantify their associated risk impact, focusing on plant transients and the wear-out of safety systems. The method, based on probabilistic safety assessment, is demonstrated by applying it to several surveillance tests conducted at boiling water reactors. The insights from this evaluation can be used to determine risk-effective intervals for surveillance tests.     

A dynamic fault tree

The fault tree analysis is a widely used method for evaluation of systems reliability and nuclear power plants safety. This paper presents a new method, which represents extension of the classic fault tree with the time requirements. The dynamic fault tree offers a range of risk informed applications. The results show that application of dynamic fault tree may reduce the system unavailability, e.g. by the proper arrangement of outages of safety equipment. The findings suggest that dynamic fault tree is a useful tool to expand and upgrade the existing models and knowledge obtained from probabilistic safety assessment with additional and time dependent information to further reduce the plant risk.     

Long-Term Stability of the NIST Standard Ultrasonic Source

The National Institute of Standards and Technology (NIST) Standard Ultrasonic Source (SUS) is a system comprising a transducer capable of output power levels up to 1 W at multiple frequencies between 1 MHz and 30 MHz, and an electrical impedance-matching network that allows the system to be driven by a conventional 50 Ω rf (radio-frequency) source. It is designed to allow interlaboratory replication of ultrasonic power levels with high accuracy using inexpensive readily available ancillary equipment.The SUS was offered for sale for 14 years (1985 to 1999). Each system was furnished with data for the set of calibration points (combinations of power level and frequency) specified by the customer. Of the systems that had been ordered with some calibration points in common, three were returned more than once to NIST for recalibration. Another system retained at NIST has been recalibrated periodically since 1984. The collective data for these systems comprise 9 calibration points and 102 measurements spanning a 17 year interval ending in 2001, the last year NIST ultrasonic power measurement services were available to the public.These data have been analyzed to compare variations in output power with frequency, power level, and time elapsed since the first calibration. The results verify the claim, made in the instruction sheet furnished with every SUS, that “long-term drift, if any, in the calibration of NIST Standard Sources is insignificant compared to the uncertainties associated with a single measurement of ultrasonic power by any method available at NIST.”     

Nuclear power plant sensor fault detection using singular value decomposition-based method

In a nuclear power plant, periodic sensor calibration is necessary to ensure the correctness of measurements. Those sensors which have gone out of calibration can lead to malfunction of the plant, possibly causing a loss in revenue or damage to equipment. Continuous sensor status monitoring is desirable to assure smooth running of the plant and reduce maintenance costs associated with unnecessary manual sensor calibrations. In this paper, a method is proposed to detect and identify any degradation of sensor performance. The validation process consists of two steps: (i) residual generation and (ii) fault detection by residual evaluation. Singular value decomposition (SVD) and Euclidean distance (ED) methods are used to generate the residual and evaluate the fault on the residual space, respectively. This paper claims that SVD-based fault detection method is better than the well-known principal component analysis-based method. The method is validated using data from fast breeder test reactor.     

Probabilistic safety assessment improves surveillance requirements in technical specifications

Probabilistic Safety Assessment is widely becoming the standard method for assessing, maintaining, assuring and improving the nuclear power plant safety. To achieve one of its many potential benefits, the optimization approach of surveillance requirements in technical specifications was developed. Surveillance requirements in technical specifications define the surveillance test intervals for the equipment to be tested and the testing strategy. This optimization approach based mainly on probabilistic safety assessment results consists of three levels: component level, system level and plant level. The application of this optimization approach on system level has shown that the risk based surveillance requirements differ from existing ones in technical specifications.     

Fault tree construction of hybrid system requirements using qualitative formal method

When specifying requirements for software controlling hybrid systems and conducting safety analysis, engineers experience that requirements are often known only in qualitative terms and that existing fault tree analysis techniques provide little guidance on formulating and evaluating potential failure modes. In this paper, we propose Causal Requirements Safety Analysis (CRSA) as a technique to qualitatively evaluate causal relationship between software faults and physical hazards. This technique, extending qualitative formal method process and utilizing information captured in the state trajectory, provides specific guidelines on how to identify failure modes and relationship among them. Using a simplified electrical power system as an example, we describe step-by-step procedures of conducting CRSA. Our experience of applying CRSA to perform fault tree analysis on requirements for the Wolsong nuclear power plant shutdown system indicates that CRSA is an effective technique in assisting safety engineers.