共查询到19条相似文献,搜索用时 203 毫秒
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设计一种基于电荷信号的远程在线自检单元,为安装于核电厂反应堆厂房的松脱部件监测系统(LPMS)的一次仪表提供快速有效的远程在线自检方法。介绍了该远程在线自检单元的设计原理和方法、硬件设计与实现,以及软件流程设计。对远程在线自检单元进行了实验室测试,测试结果表明,在空载输出5 V低电压工作条件下可满足250 m的远程在线自检要求,同时对集成了该远程在线自检单元的国产化LPMS样机进行了鉴定试验,试验结果验证其满足工程应用环境。集成了远程在线自检单元的2套国产化LPMS产品已在巴基斯坦的恰希玛核电厂C-3/C-4机组进行了成功应用,以低成本和高效率实现了反应堆装料运行期间LPMS一次仪表的在线检测。 相似文献
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介绍了田湾核电站水-水高能反应堆(VVER)机组松脱部件监测系统(LPMS)的设计和设备结构组成,描述了其设计与美国核管会(NRC)RG1.133相关条款要求的差异。基于这些差异以及VVER机组的特殊性,分析了拟采取的改进措施存在的困难和不利影响。为执行与NRC RG1.133中安全要求相当的功能,在田湾核电站3号机组调试阶段开展了LPMS系统的功能补充试验,获取与压力容器相关的传感器信号的响应,验证了目前的传感器布置方式能满足NRC RG1.133的设计要求。 相似文献
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核电厂数字化仪控系统的国产化对于我国的核电发展具有重要意义,针对其中对于模拟量采集模块的技术要求,自行研制出了一款采集精度达到万分之二AI模块,对于输入阻抗、元器件温度漂移、隔离等影响采集精度和稳定度的主要因素进行了原理性分析,阐述了模块的设计思路。长期运行试验结果显示模块的精度、温漂、共模和差模抑制比均达到设计要求.目前该模块已应用于核电厂现场。 相似文献
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为满足核电厂全范围模拟机对严重事故过程仿真的需求,自主开发了严重事故仿真软件SimSA,能模拟从设计基准事故到严重事故的主要事故过程,并能准确给出相关进程的计算结果。SimSA包含3大主要模块:热工水力模块(Therm)、堆芯行为模块(Core)以及安全壳行为模块(Cont)。其中,Therm与Core两个模块的耦合过程中采用了SCDAP/RELAP5相似的基于过程机理的耦合方法。本文结合SimSA软件的具体情况介绍了这种耦合方法的实现过程,并采用耦合后的程序对大破口叠加安注失效及全厂断电叠加辅助给水丧失两个典型初因事故导致的严重事故序列进行了计算,将计算结果与相同初始条件下MAAP4的计算结果进行对比分析。结果表明,SimSA中采用的这种耦合方式是成功的。 相似文献
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为保证国产化的核电厂集散控制系统(DCS)的安全性和可靠性,必须对其实施验证和确认(V&V)过程.为使V&V过程顺利进行,建立适用的V&V体系是十分必要的.本文提出了V&V体系的建立,该体系包括:明确具有层级关系的V&V指导文件;定义支持DCS研发生命周期的V&V过程;指定DCS软件完整性等级的划分方案以及确定V&V独立性、人员资质和工具的要求.该V&V体系适用于核电厂DCS软件研发项目,并对促进自主化开发和取证工作具有非常重要的意义. 相似文献
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为建立基于现场可编程门阵列(FPGA)的反应堆保护系统的可靠性模型,以对系统安全提供有效的分析与验证手段。本研究采用故障树、随机Petri网模型,对CANDU堆1号停堆系统(SDS1)单通道进行可靠性建模与分析。对故障树模型分析得到最小割集,以顶事件发生概率作为系统故障概率,在考虑故障检测、维修与定期试验情况下对随机Petri网模型进行仿真得到系统的拒动概率。研究结果表明,故障树和状态空间方法存在一定局限性,随机Petri网能够反映故障检测与定期试验对反应堆保护系统的影响,可以动态地反映系统可靠性,并且避免了状态空间爆炸问题。因此,本研究建立的随机Petri网模型适用于反应堆保护系统的可靠性建模。 相似文献
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在分析M310堆型核电站辐射屏蔽设计中由于工具限制存在的问题以及“华龙一号”堆型核电站辐射屏蔽设计提出的要求的基础上,从程序界面、输入接口、计算功能和辐射场应用扩展4个方面提出先进压水堆核电站辐射屏蔽优化设计对于蒙特卡罗(MC)方法的要求。MC方法在“华龙一号”辐射屏蔽优化设计的应用实践表明,基于MC方法的计算程序在程序界面、输入接口和辐射场应用扩展方面进一步提升之后,可在先进压水堆核电站辐射屏蔽优化设计方面发挥巨大的作用,显著提升核电站辐射屏蔽优化设计的水平。 相似文献
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通过梳理DI&C-ISG-04标准和ACPR1000核电机组对优先级管理系统(CIS)的功能要求,参考CPR1000核电机组CIS方案中的经验反馈,分析CIS设计中的诸多难点,提出了一套基于和睦系统(FirmSys)的ACPR1000核电机组保护系统CIS方案。相比CPR1000核电机组,ACPR1000核电机组的CIS方案采用了多种设计手段进行优化,如自主化和国产化设计、更优的防软件共因故障设计、更可靠的在线定期试验设计、模块化及多接口设计、就地功能设计。该设计方案已成功应用于ACPR1000核电机组,运转良好。因此本研究提出的CIS方案切实可行。 相似文献
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Loose Parts Monitoring signals in the control room of the nuclear power plant come in through multiple channels and are presented as graphs on the display devices. It involves a lengthy and complicated process to determine the size, mass, speed, and impact location of the loose part when the signals are collected and processed. In this work, a simple and efficient model for determining the impact location of the loose part using the Least-Sum-of-Square-Errors (LSSEs) method combined with iteration has been developed based on the phase distortion of the impact signal envelopes. The signal peak point shifts to the right on the time axis when the sensor is located farther away from the impact location. This method provides a good estimation of the impact location and can be used as an alternative to existing calculations based on other attributes of the impacting signal. To automate the backend portion of the LPMS algorithm, interpolation was used for compensating the impact attenuation effect and log-log regression was also employed to determine the impacting part size and impact velocity, and the result turned out to be well in line with the manual calculations. The automated algorithm will improve the efficiency of the LPMS software. 相似文献
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郑伟智 《核电子学与探测技术》2012,32(4):438-441,452
在核电站保护系统中应用基于数字化技术的安全级DCS已替代模拟技术成为主流,因为核电站的安全性要求很高,所以DCS技术的可靠性至关重要。为了确保应用DCS技术设计的可靠性,通过分析相关法规、标准的要求,总结了安全级DCS设计须进行的质量鉴定项及软件验证和确认过程,并结合当前主要应用的几个安全级DCS产品的技术特点,提出了安全级DCS设计开发中应考虑的控制器、智能IO模块、优选驱动模块以及通信等关键技术的要点。 相似文献
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Shaoxiang Ma Ming Zhang Linglong Xia Dehong Chen Xueliang Zhang Chuliang Wang Kexun Yu 《Journal of Fusion Energy》2014,33(6):693-701
To energize the gyrotrons of the electron cyclotron resonance heating system, high-voltage power supply (HVPS) at 100 kV/60 A was built on J-TEXT tokamak. The HVPS was based on pulse step modulation (PSM) technology. This power supply has many advantages, including low energy storage and a short protective time in the event of a short circuit fault. In this study, we analyze and compare several common control strategies for PSM power supply. To enhance dynamic performance, the improved queue-up PSM control strategy was proposed. The control algorithm was generated using a controller based on parallel card interface extensions for instrumentation (PXI) technology, which conforms to the control, data access, and communication standard of the ITER. This controller also operates the modules of switch power supply. Experimental results show that the control system is effective and that the PXI controller can rebalance the output voltage and frequency in 60 μs when the module malfunctions under the improved system. Furthermore, the algorithm for the PXI controller is easy to develop and does not require much resources. 相似文献
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采用代码生成技术可大幅提高软件开发的质量和生产率,降低软件开发风险。目前已有代码生成器多是基于UML模型驱动技术,不能很好适应核电数值计算软件的开发需求。本文针对科学计算类程序的设计特点,开发了基于C#的代码生成器FCG。FCG可根据输入元数据自动生成Module变量定义Fortran代码,并根据元数据自动生成动态变量的内存分配接口和数据访问接口,方便程序直接调用。目前,FCG已应用于堆芯设计和系统分析一体化平台(COSINE)软件的开发过程,实践证明,FCG可极大提高核电软件的开发效率,同时降低软件开发的缺陷率。 相似文献
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At the request of the U.S. Nuclear Regulatory Commission (NRC), an assessment of the technical development status of loose-parts monitoring systems (LPMS) and their performance record to date in commercial light-water-cooled nuclear reactor plants was made during the spring of 1977, using an on-site personal interview and equipment demonstration approach. Our study revealed that while presently demonstrated LPMS technology does indeed provide a capability for detecting the presence of those relatively massive loose parts that would likely constitute a serious operational or safety hazard to the plant, it unfortunately affords little information useful to the determination of the parts' safety significance and has not yet attained the levels of sophistication and reliability ordinarily associated with safety systems. We also found a definite need for specification of the functional requirements for LPMS, in the form of a clear and comprehensive statement of NRC policy regarding the formulation and implementation of safety-oriented, yet operationally practicable, loose-parts monitoring programs for both existing and future nuclear generating stations so that overall objectives of both the utilities and the regulatory agency might be satisfied simultaneously.
While it is our best technical judgment that loose-parts monitoring programs providing reliable detection (but not characterization) capabilities could be implemented with today's technology, the path on which the nuclear utility industry should proceed in order to meet NRC expectations is not completely clear. A Regulatory Guide entitled “Loose Part Detection Program for the Primary System of Light-Water-Cooled Reactors,” soon to be issued for public comment, constitutes a first step towards satisfying this need for guidance and goal establishment. 相似文献