共查询到18条相似文献,搜索用时 187 毫秒
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简要介绍了蒸汽发生器水位控制系统的运行方式和试验方法。试验项目包括旁通阀控制试验、主给水阀控制试验和旁通阀与主给水阀的切换试验。文中给出了试验结果,即在液位扰动和核动率扰动时,蒸汽发生器液位的变化过程。经过两个月的运行和瞬态试验,证明蒸汽发生器水位控制系统满足设计要求。 相似文献
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应用瞬态分析专用程序建立了CPR1000蒸汽发生器几何模型,对CPR1000蒸汽发生器在功率运行期间停运一台主泵时的热工水力瞬态响应、主蒸汽管道破裂和蒸汽/主给水流量同时+10%阶跃扰动工况下的瞬态响应进行了模拟与分析,获得了蒸汽发生器内部热工水力参数如流量、温度、换热系数的响应特性,分析结果表明,瞬态分析模型满足蒸汽发生器设计瞬态分析的要求。 相似文献
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压水堆蒸发器水位调节失控跳堆分析及在线诊断调整 总被引:1,自引:0,他引:1
分析了核电站引发蒸发器给水控制系统(ARE)水位跳堆的主要原因和薄弱环节,建立了在功率运行状态下进行ARE主阀调节偏差在线调整和旁路阀调节偏差在线调整技术,提出并实施处理方案,解决了压水堆机组在启停过程中水位容易发生失控的技术难题. 相似文献
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为了满足AP1000核电站设计寿命60年的需求,核岛设备蒸汽发生器锻件的强度和韧性要求比CPR1000核岛主设备都有所提高,加之尺寸增大,使得AP1000蒸汽发生器锻件的制造难度加大,对其变化认识不够,不仅锻件的产品质量不稳定,而且后序的焊接也可能出现质量问题,文章通过对比分析AP1000核电蒸汽发生器锻件与CPR1000锻件的变化,提出了采取措施的方向。 相似文献
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AP1000核电机组60 a的设计寿命对二回路水质提出了更高要求。为保证水质并提高系统固有安全性,海阳核电站凝结水精处理采用无阀旁路工艺,通过增加后置过滤器、改进再生设备、优化再生工艺来控制硫酸根的生成,防止蒸汽发生器不锈钢腐蚀;凝结水精处理系统调试时按照西屋分包模式进行,对调试过程中出现的一些情况进行了经验反馈。 相似文献
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在厂外主辅电源切换时,为避免因一回路主循环泵(简称主泵)运行引起反应堆保护停堆或电机辅助绕组启动,对主泵惰转特性及转速控制进行分析,分别对快切和慢切工况下主泵的快速飞车启动和搜频飞车启动模式进行研究,给出了不同模式下主泵的最低转速预测模型,分析出了快切工况(断电1.5 s)下主泵最低转速为708.3 r/min,慢切工况(断电10 s)下最低转速为341.2 r/min。在主泵水台架上,用1.5 s和10 s断电试验来模拟厂外主辅电源快切和慢切工况,试验结果表明,快切工况下主泵最低转速为689r/min;慢切工况下主泵最低转速为346.7 r/min。最低转速预测值与试验值吻合较好,偏差小于3%。试验验证了主泵在主辅电源切换工况下的运行特性,可实现快切不导致反应堆保护停堆,慢切不导致辅助绕组启动,对反应堆安全运行具有指导意义。 相似文献
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闭式布雷顿循环是第4代高温堆核能系统的关键技术之一,其典型的动态过程是旁路阀调节。为分析这一过程,建立了循环中关键部件的动态模型,其中压气机在径向平衡模型基础上耦合了对附面层发展的预测,兼顾了计算效率与准确性;换热部件模型基于双曲型守恒律方程,对工质的热物性和参数的快速变化有较好的适应性。在此基础上根据回路的质量守恒和压力平衡原则将各部件的模型耦合,建立了系统的动态模型。由于旁路阀调节是氦气透平发电系统主要的功率快速调节手段,瞬态效应较为显著,以模块式高温气冷堆(HTR-10GT)旁路阀开启后的过渡过程作为算例,分析了主要循环参数的响应特性,并通过分析,给出了降低输出功率的机制。计算结果表明:系统的容积惯性对旁路阀调节的响应速度影响较大,而阀门的开度则决定了系统在末态的输出功率;回热器的温度冲击现象可能发生在调节过程中,但可通过两旁路阀联动的方式缓解;反应堆出口温度变化幅度很小,因此反应堆模型的准确程度对结果基本无影响。 相似文献
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当前蒸汽发生器(SG)液位控制系统手自动切换信号复制回路的设计中,液位控制器运算基准为切换时的汽水失配信号,主给水流量调节阀由手动模式切到自动模式后导致SG液位控制系统失去快速调节给水流量的前馈作用。针对该问题,结合阳江核电厂4号机组SG液位高高跳堆事件,提出了针对手自动切换操作方式和系统设计的2种优化方案。针对操作方式的优化,在主给水流量调节阀投自动前,手动平衡汽水流量;针对系统设计的优化,增加汽水失配判断环节和前馈自动补偿环节。通过SG液位扰动试验证明,所提出的优化方案能有效提高手自动切换后控制系统的调节速度、减小超调量,对核电机组安全运行水平提升有重要贡献。 相似文献
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《等离子体科学和技术》2020,22(4):45603
Ion cyclotron wave resonance heating system(ICRH) which is one of the most important auxiliary system in EAST provides conditions for heating the plasma. In order to make the whole transmission network of ICRH form the required state, the coaxial switching system was developed, which mainly consists of 11 same coaxial switches. Each coaxial switch has a controller with an RS485 communication interface and is able to switch between two states. All controllers are integrated to an RS485 hub which connects to the computer. A master computer software is developed to control the coaxial switching system so as to achieve the state needs of ICRH. Moreover, several rounds of experiments show that the coaxial switching system operates reliably. The coaxial switching system has already been applied to normal use currently. 相似文献
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This paper describes a performance model for the transient analysis of helium turbine system. Governing equations have been derived from integral forms of unsteady basic conservation equations. The one-dimensional model is employed for flow-paths except turbine and compressor, which are considered as zero-dimensional components and volume-less treatment is employed. Component mathematical model results in a set of ordinary differential equations and algebraic equations. The simulation code is established on MATLAB, and the ordinary differential equations are solved a variable order solver of MATLAB, ode15s. The accidents of loss of load and loss of feedwater to precooler and intercooler, the transients of recuperator and the decreasing heat transfer capacity of intermediate heat exchanger are simulated respectively. The analysis of calculated results verifies the present model. The effects of bypass valve size and thermal inertia of the recuperator wall are also studied. The simulation results show that throttle size of bypass valve has important influence on the characteristics of turbine system and should be carefully selected to satisfy the requirement of system control and safety. 相似文献
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《Annals of Nuclear Energy》2005,32(5):479-492
We have developed a method for detecting and diagnosing a disk wear failure and a foreign object failure among the various failure modes of check valves. The method is based on the acoustic emission sensors which can detect the sound wave of the leakage flow and the estimation of the power spectral densities with an auto-regressive model. For validating the method, we implemented a hydraulic test loop with an artificially failed check valve. We have found that the frequency spectrums from the acoustic signals are strongly dependent on the failure modes of the check valve and that they are nearly independent of the failure size and operating pressure through an estimation of the power spectral density with an auto-regressive signal processing model. In addition, the root mean square values of the acoustic signal and the amplitudes of the power spectral density as well as the loop pressure have a strong dependency on the failure size in each failure mode of the check valve. We developed a diagnosis algorithm by using neural network models in order to identify the type and size of the failure in the check valve. The diagnosis algorithm consists of a hierarchical model composed of three back-propagation neural networks. The results of our research and the experiments show that the diagnosis algorithm is proven to be a good solution for identifying the failures of the check valves without any disassembling work. 相似文献
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J.R. Fitch 《Nuclear Engineering and Design》1989,111(2)
This paper treats the problem of correctly accounting for the quasi-static component of the response of a thin-shell structure to a dynamic loading which originates from a pressure disturbance within the body of a contained fluid. The importance of quasi-static structure response has been observed in BWR safety/relief valve (SRV) actuation tests which produce a pressure oscillation in the suppression pool as a consequence of the expansion and contraction of bubbles formed from air expelled from the SRV pipeline. The problem is treated within the context of a finite-element methodology which has been previously developed for the coupled analysis of a linear elastic structure in contact with a linear acoustic fluid. For problems involving a large number of degrees of freedom, the efficient application of this method requires reduction to a set of normal modes approximating the response of the coupled fluid-structure system. The coupled modes are synthesized from the fluid properties and a set of normal modes describing the behavior of the structure in the absence of the fluid. The proposed solution to the problem is to append a shape function, representing the quasi-static component of the structural response, to the set of modes computed by standard eigenvalue extraction. The success of the method is demonstrated by comparison of calculated results with measured structural response from a typical SRV test. 相似文献