首次装料的核安全和核监测

本文介绍秦山核电厂首次装料程序、装料中的核安全与核监测,以及装料试验用的临时核测仪表和设备。首次装料试验结果表明,仔细筹划、充分准备是装料试验成功的基础,试验结果满足验收准则。     

秦山核电厂核测系统的调试

本文介绍了秦山核电厂核测系统在装料前后、零功率和功率试验阶段的调试过程、方法和主要数据以及源量程、中间量程和功率量程之间的复盖情况。最后对将来核测系统的设计提出了几点建议。     

Event Priority Instrumentation System for Nuclear Experiments on Scientific Satellites

The number of information bits per unit time, or data rate, which can be telemetered back to earth from a scientific satellite is limited by restrictions on weight, volume and power. Thus, each experimenter (generally one of many) is allotted a very limited data rate capability. In nuclear experiments, where a wide variety of events may occur per unit time, use of this rate capability may be optimized by selection of events on a priority basis. Described here is an event priority instrumentation system developed for use in scientific satellites. The system allows for the selection of the highest priority event occurring during a telemetry sequence. Also, provision is made for periodically changing the order of priority. All circuitry was designed and developed to minimize weight, volume and power drain and to maintain stable characteristics while unattended for periods as long as one year. The operating temperature range is -20°C to 60°C.     

Recent Developments in Nuclear Medicine Instrumentation

Nuclear Medicine instrumentation, as is the case for most sophisticated technologies, is constantly being improved through the introduction of new devices as well as through refinements in devices that are available from several manufacturers. The purpose of this text is to describe the recent developments that have led to improvements in the performance of instruments currently being used for routine diagnostic studies and to also describe some of the new devices that are becoming available.     

反应堆堆外核测量系统的实时仿真

堆外核测量系统实时仿真是核电厂全范围培训模拟器的重要组成部分。本文给出一种基于测量原理的功能仿真处理方法,利用堆芯物理仿真计算出堆芯中子通量密度．建立了堆外核测量值与反应堆内三维中子通量密度分布之间的拟合公式．根据反应堆物理计算或功率刻度实验确定拟合系数．可以实时准确仿真堆外核测量系统,满足核电厂全范围培训模拟器的要求．     

Analytical Method for Recalibration of Incore and Excore Nuclear Instrumentation System of PWRs

In pressurized water reactors (PWRs) of nuclear power plants, it is periodically required to recalibrate the correlation between the incore and excore nuclear instruments, where the recalibration guarantees the accurate monitoring of incore axial power distributions by excore instrumentation. In order to obtain the correlation between incore power distribution and excore detector response, however, it is necessary to perturb the axial power distribution of the reactor by control rods or to introduce a xenon spatial oscillation.

In this paper a simplified analytical method that eliminates such perturbations is proposed to evaluate the correlation between incore power distribution and excore detector currents which is utilized to recalibrate the nuclear instrumentation system. This method provides as good an accuracy as that obtained by conventional methods.     

浅谈核电厂仪表控制系统电磁兼容性要求

针对现有核电厂设备电磁兼容性测试的不足,探讨了国内核电厂仪表控制系统在核电厂电磁环境下的电磁兼容性要求和评价方法。建议加强核电厂仪表控制系统的电磁兼容性设计,以保障核电厂安全、稳定的运行。     

核电站保护系统多样化手动驱动系统设计

针对基于计算机技术的数字化仪控系统可能存在软件共因故障问题,设计了一个安全系统系统级手动驱动系统。该系统用以在计算机技术实现的保护系统失效后执行安全功能。本文介绍了与该系统相关的安全系统的系统级操作、事件级的电站状态监视、定期试验、非计算机化设备、独立性、多样化等内容。这些特点能够保证在采用计算机技术的反应堆保护系统失效后,提供有效的安全功能执行手段,缓解事故后果。该系统弥补了计算机化仪控系统的弱点,能够防止软件共因故障。     

核仪表在钢铁工业的应用与发展

核仪表(核子控制系统)具有非接触测量、精度高、反应快、稳定性好,采用计算机技术实现数字化、智能化、网络化的特点,因此已越来越广泛地应用在生产过程复杂、自动化程度高、现场环境比较恶劣的钢铁制造流程在线检测,并在实时控制系统中作为不可缺少的基础仪表提供各种重要检测数据。本文主要介绍核仪表在国内外钢厂应用现状、发展、技术与经济效益。     

数字化核仪表系统样机堆上试验及验证

针对目前国内核电厂核仪表系统设备主要依赖进口的现状,设计研发了一套数字化核仪表系统样机,系统样机主要包括中子探测器组件、信号调理和处理样机以及信号监控设备。通过介绍样机在商用堆上的安装和试验情况,详细分析了反应堆启堆、升功率、满功率及降功率运行期间的试验数据。试验结果表明,中子探测器与信号调理和处理样机配合良好,整套系统样机运行稳定可靠。      

核电厂堆外中子测量系统闪发高计数率问题研究

从故障现象、原因排查和解决措施三个方面,分析了我国核电厂近期发生的堆外中子测量系统闪发高计数率异常中所涉及的电缆接头问题和探头故障问题,提出了核电厂应关注堆外中子测量系统设备制造和安装的质量等建议,为解决和避免类似的堆外中子测量系统闪发高计数率问题提供借鉴。     

压水堆核电站的启动与初期运行

本文综合介绍世界各地区压水堆核电站启动及初期运行中的经验教训。其范围涉及管理、堆芯及核燃料、电气、控制、仪表、回路、机械及水化学等专业。文中结合我国情况,提出了应注意的问题及建议。     

核电厂安全相关仪表和控制系统的电磁兼容性要求及评价

分析了先进的仪表和控制系统的技术发展状况 ,及其新技术应用对电磁环境兼容性的影响 ,并在我国核安全现状基础上 ,通过国外一些相应的技术经验和信息 ,探讨了运行在核电厂环境下的安全相关仪表和控制系统对电磁干扰、射频干扰和电源波动的兼容性要求及评价方法 ,为我国建立和健全在这一领域的法规和要求提供借鉴     

大亚湾核电站全范围模拟机硬件I／O实现

广东大亚湾核电站全范围模拟机(以下简称模拟机)是从法国汤普森公司引进的。它是用数字仿真技术对大亚湾核电站主控制室进行1:1高保真模拟的大型设备,用于培训核电站的操作运行人员、系统分析包括对操作规程的验证等。模拟机的 I/O 接口系统是计算机与各种开关、仪表交换信息的桥梁。本文力求从数据传输的角度,结合程序流程图论述 I/O 接口系统的工作原理。     

基于NuPAC的核电厂反应堆保护系统

现场可编程门阵列（FPGA）技术作为一种不同于CPU技术的数字电子技术,越来越广泛地用于核电厂安全级仪控系统。本文介绍了基于FPGA技术的核电厂反应堆保护系统平台NuPAC及反应堆保护系统的结构,分析了NuPAC平台在简化系统设计、独立性和多样性等方面对反应堆保护系统结构的改进。此外,分析了FPGA技术在提升反应堆保护系统的确定性、安保性和可持续性等方面的优势,介绍了反应堆保护系统的需求分析及其挑战。本文将为今后国内其他基于FPGA技术的核安全级仪控系统的开发提供参考。     

Nuclear Power Plant Control beyond the 1980s

Designers of nuclear power plant control and instrumentation systems are being pushed by an electronics technology that currently passes through several generations of development during the time taken to design and bring a plant into production. Despite the success of existing designs and the pressure to stick to them, the rapidity with which new components become available and others drop from the suppliers' shelves, require that we give attention to system architectures that are more tolerant of this situation. A distributed data base, containing both on-line and archival information, made available to all systems of a nuclear power plant by means of a highly reliable communications medium, could form the basis for such an architecture. It could not only solve this problem of rapid component development but also provide for complete and comprehensive plant control and surveillance. The possibility of implementing such schemes in an operating plant is probably ten years away but development must begin now if the new electronics technology is to have a planned place in the architectures of the future. At the Chalk River Nuclear Laboratories a long range program is underway. It is exploiting extensive additions that were needed in the data acquisition and processing capability associated with engineering experiments in the large research reactors NRU and NRX.     

Tory II-C Nuclear Instrumentation System

The design of the nuclear instrumentation system for the Pluto series of nuclear ramjet test reactors is an attempt to provide a very flexible nuclear sensing system that will be adequate for Tory II-C and following test reactors. The nuclear detectors will be exposed to the leakage neutron flux from the reactor during operation. Since the leakage flux is proportional to reactor power, the neutron detectors will give a measure of reactor power. A difficulty in providing nuclear instruments for this reactor is the uncertainty in the neutron energy spectrum of the leakage flux at the detectors. Since detector response varies with neutron energy, a large margin of flexibility is desirable. A difficulty which may be encountered is a significant shift in neutron energy spectrum at high power and temperature. This would make indicated nuclear power nonlinear with calorimetric power. A difficulty in insufficient instrument overlap was encountered with the Tory II-A experiment where a large margin of flexibility would have been useful. The detector placement for the Tory II-A experiment had the power range detectors in line with the reactor and main air pipe. At high air flows there was a much greater mass of air between the detectors and the reactor, allowing fewer neutrons to reach the detectors per unit reactor power. This is the reason for the power range detectors being placed off to the side of the Tory II-C test vehicle. Not all difficulties can be foreseen, but provision is made where possible to overcome them.     

基于数值微分核脉冲信号数字处理方法

核反应堆核测量系统测量探测器输出的核脉冲信号,该信号后沿拖尾很长,在计数率较高时容易产生信号堆积和基线漂移等问题,导致源区计数率测量上限仅能达到105 Hz左右。文中基于数值微分方法,采用数字处理技术,在时域上分析了核脉冲信号经过前置放大、信号成形、低通滤波和脉冲甄别后的输出,并利用探测器实测信号进行了仿真。仿真结果表明,基于数值微分的数字处理方法可以实现相邻0.4 μs脉冲信号的识别和测量,将源区测量计数率上限提升到2×106 Hz以上。      

秦山核电厂反应堆保护系统及其相关设备数字化改造规划和实施策略

秦山核电厂采用数字化技术改造了基于模拟技术的反应堆保护系统。与此同时,采用同一数字化安全仪控平台对堆外核测系统进行了改造。文章结合该厂原有系统的历史和现状,在广泛了解目前国际上数字化安全仪控平台的发展状况、国外核电厂在该领域的应用现状的基础上制定适合秦山核电厂工程实际的改造规划和"以我为主,中外合作,充分利用国内技术力量"的实施策略。分析了影响和制约在役核电厂反应堆保护系统及其相关设备改造的主要因素,并对可实施性作总体评估,以了解改造过程中所面临的问题和困难,预先准备相应对策,确保技术改造目标的实现。     

田湾核电站物项的安全分级

核电站物项的安全分级工作中应特别注意全局性、适度性、均衡性这3项原则．物项安全分级的;基本方法,一般是根据物项（部件）的承压外壳损坏对安全的影响,对物项的安全功能进行分级田湾核电站采用的是俄罗斯VVER-1000／428型反应堆装置,其物项安全分级主要采用俄罗斯法规标准：电气和仪控设备采用IEEE-308（80）标准,分为1E级与非1E级;仪控系统及设备的安全分级采用国内标准GB／T15474—1995,分为安全1E级,安全相关SR级和NC非安全级,田湾核电站物项的安全分级必须经中国核安全当局审批并满足中国核安全法规要求．