基于CIMS的核电厂集成管理系统设计研究

以计算机与现代集成制造系统（CIMS）的“集成”思想为指导,提出了核电厂集成管理的新方法。对核电厂集成管理系统的设计进行了分析。采用数据库和工程数据管理技术（PDM）实现核电厂异构环境下的信息集成。针对核电厂的特点和管理需要,先将核电厂的所有工作按性质分为不同的类型,然后在总系统下设计若干个分系统,每个分系统完成一种类型的管理工作.在基于CIMS的集成环境下．每个分系统既相对独立又相互联系,通过全局信息共享系统实现信息共享。该方法为充分利用核电厂的人力,物力与信息资源,构建核电厂科学的管理体系提供了一个新思路。     

核电工程建设进度控制的关键路径分析

以M310堆型为基础．结合大亚湾、岭澳工程的建设经验．研究核电工程建设进度控制的关键路径分析表明．核电工程建设的关键路径是核岛土建、核岛安装、与一回路冷态调试相关的单系统调试及联合调试。对于核岛土建．关键路径在反应堆厂房主体土建施工、预应力张拉、重点区域的土建房间移交和关键土建／安装接口移交;对于核岛安装．有4条关键路径：对于调试．分为冷态调试相关的16个单系统调试和联合调试两个阶段。     

Interface mixing induced by swift heavy ions at metal-oxide/silicon interfaces

It was observed previously that ceramic/ceramic bilayers were very sensitive with respect to the electronic stopping power S_e, i.e. strong interface mixing, scaling with , occurred if a threshold S_ec was exceeded. The threshold seemed to be determined by the higher track formation threshold of two constituents forming the bilayer. Although no track formation has been observed in crystalline Si even for Uranium projectiles, interface mixing was observed previously for some Si-multilayers.

In this paper we report on the interface mixing of NiO, Fe₂O₃, TiO₂ on Si due to irradiation with 90–350 MeV Ar-, Kr-, Xe- and Au-ions at 80 K at fluences up to 9E15 ions/cm². Interface mixing, analyzed by means of Rutherford Backscattering Spectrometry (RBS), is found for these bilayers, too. But the threshold for intermixing is significantly higher compared to the ceramic/ceramic bilayers. This observation could be an evidence for the threshold being determined by the Si-layer. In contrast to NiO/Si and Fe₂O₃/Si, where an usual random walk mixing Δσ² = kΦ was observed, the interface broadening Δσ² for TiO₂/Si is found to scale nonlinearly with the ion fluence, which indicates that mixing is driven by a chemical solid-state reaction. At higher fluences plateaus form at the low energy Ni-edge of the RBS spectra. The plateaus indicate phase formation. X-Ray diffraction spectra does not show any evidence for new crystalline phases.     

Optimization of a dynamic uncertain causality graph for fault diagnosis in nuclear power plant

Fault diagnostics is important for safe operation of nuclear power plants (NPPs).In recent years,data-driven approaches have been proposed and implemented to tackle the problem,e.g.,neural networks,fuzzy and neurofuzzy approaches,support vector machine,K-nearest neighbor classifiers and inference methodologies.Among these methods,dynamic uncertain causality graph (DUCG) has been proved effective in many practical cases.However,the causal graph construction behind the DUCG is complicate and,in many cases,results redundant on the symptoms needed to correctly classify the fault.In this paper,we propose a method to simplify causal graph construction in an automatic way.The method consists in transforming the expert knowledge-based DCUG into a fuzzy decision tree (FDT) by extracting from the DUCG a fuzzy rule base that resumes the used symptoms at the basis of the FDT.Genetic algorithm (GA) is,then,used for the optimization of the FDT,by performing a wrapper search around the FDT:the set of symptoms selected during the iterative search are taken as the best set of symptoms for the diagnosis of the faults that can occur in the system.The effectiveness of the approach is shown with respect to a DUCG model initially built to diagnose 23 faults originally using 262 symptoms of Unit-1 in the Ningde NPP of the China Guangdong Nuclear Power Corporation.The results show that the FDT,with GA-optimized symptoms and diagnosis strategy,can drive the construction of DUCG and lower the computational burden without loss of accuracy in diagnosis.     

M310核电厂严重事故下稳压器隔间氢气风险分析

基于GASFLOW程序,选取对M310核电厂稳压器隔间内氢气风险极为不利的两种事故工况,对安全壳内氢气风险进行了分析计算。模拟结果显示:在所研究的工况条件下,卸压箱隔间、波动管隔间、稳压器隔间及穹顶区域内,只有波动管双端断裂事故在早期氢气集中释放阶段,出现了稳压器隔间内FA准则数大于1的情况,其他隔间及其他工况下所有隔间内的FA准则数和DDT准则数均不会超过1。即,所研究隔间内均可以排除燃爆转变风险。破口隔间内部氢气浓度分布主要受源项氢气浓度以及混合气体夹带作用的影响,不同位置的氢气浓度变化存在显著差别。安全壳大空间的氢气浓度呈层状结构,随着时间推移,层状结构向下推移,安全壳大空间氢气浓度分布呈均匀化趋势发展。     

核电站氚的排放量及浓度限值比较分析

氚是核电站运行过程中向环境中排放较大的放射性核素之一,控制核设施中氚的产生和排放量越来越引起人们的重视。本文通过分析核电站产生氚的主要途径,结合国际上的运行经验参数,对比分析了不同国家、不同堆型核电站氚的排放量和浓度限值。分析结果表明:三十年间,全球核电站流出物中气态氚的排放量显著高于液态氚,重水堆是各堆型核电站中氚排放的主要贡献者,也是氚排放所致公众剂量的主要来源。为了更加有效的控制氚的排放,法国等国家核安全监管机构根据电站的装机容量、排放工艺、堆型等制定了各自国家核电站氚的年排放总量限值;加拿大等国的监管机构根据剂量限值制定了导出排放限值,该值的优点是便于审查核电站正常运行时氚的排放量;其它核电国家则是以剂量限值的形式提出了氚的排放限值。     

Assessment of thermal aging embrittlement in a cast stainless steel valve and its effect on the structural integrity

This paper analyzes the thermal aging embrittlement occurred in a cast stainless steel valve, which is part of the reactor water clean-up (RWCU) system of a Spanish boiling water reactor (BWR) nuclear power plant. The aim is to estimate the current and future state of the material and the corresponding structural integrity of the valve. Given that there is no data available for the experimental characterization of the material, the evolution of the mechanical properties (fracture toughness, yield stress, flow stress and Ramberg-Osgood parameters) has been estimated using the ANL procedure.With the obtained estimations, the critical crack size has been calculated using the European procedure FITNET FFS and the ASME Code.This analysis considers not only the evolution of the mechanical properties up to now but also its future evolution in case there is a life extension of the plant until year 2029.     

基于粗糙决策模型的核电厂故障诊断方法

将粗糙集和信息熵相结合,提出了改进的决策树ID3算法,并提出了基于此算法和粗糙集约简算法的故障诊断方法.将该方法用于核电厂故障诊断.结果表明,该方法具有良好的故障诊断性能,可在核电厂故障诊断领域中应用.     

BP神经网络改进算法在核电设备故障诊断中的应用

根据训练误差大小自适应调整神经元输入特性参数,并应用改进的遗传算法对神经网络的权值和隐含层数目进行优化,对传统的人工神经网络误差反传算法进行了改进,使训练算法的收敛速度大大提高.将人工神经网络技术和改进的BP网络训练算法应用于核电设备故障诊断,并以核电蒸汽发生器U形管破裂为例,建立了故障诊断模型.仿真结果表明,该算法的应用是可行的.     

Recent activities in the field of Nuclear Operational Management and Nuclear Safety Engineering

Recent activities in the field of Nuclear Operational Management and Nuclear Safety Engineering, the studies related to risk analysis methodology, design, and operational management, physical phenomena, and emergency preparedness and nuclear security, have been progressed. Especially, ‘risk analysis methodology’ and ‘design and operational management’ are the main categories of the field, in which more than half of published articles on Journal of Nuclear Science and Technology are related to these categories.