旋启式止回阀关阀水锤优化分析

建立了双泵并联给水系统数学物理模型,针对旋启式止回阀关闭过程中形成的水锤进行编程计算,分析作用在止回阀阀板上的力矩以及阻尼扭簧力矩对关阀水锤的影响。结果表明：在双泵并联给水系统中,旋启式止回阀在关闭时会产生明显水锤,作用在阀板上的力矩对水锤的作用效果有一定影响,选择合适的止回阀阀板材料以及加装合适的弹簧可有效缓解水锤危害。     

考虑流-固耦合效应的空间管道水锤方法研究

介绍耦合水锤理论的4方程模型和其求解方式,以及利用计算流体力学(CFD)计算流-固耦合的方法,并采用文献作为算例进行水锤流-固耦合的计算。通过CFD的经典水锤计算,为流-固耦合计算选定计算格式和网格,同时与文献进行比较。结果表明,本文所用的方法可用于较复杂的管道水锤的流-固耦合计算。     

管道流体瞬态—水汽锤计算原理

文中介绍了核电站管道中流体瞬态——水汽锤的计算原理;既适用于液体介质的水锤计算,也适用于可压汽体的汽锤计算.对于一些典型管道部件的处理方法,文中也作了讨论。     

核电厂重要厂用水泵出口管道振动分析及处理

为了解决3SEC004PO出口管道振动问题,依据水锤压强的计算公式,分析了含气量对有压供水管道水锤压强的影响,研究结果表明有压供水管道内含有气体会进一步增加水锤压强值,且含气量越大水锤压强升高值越大,所含气体的温度越高,水锤压强升高值越大。基于水锤理论、功能原理、动量定理以及虹吸效应具体分析了3SEC004PO出口管道振动的根本原因,并针对根本原因采取针对性的改进措施,解决了3SEC004PO出口管道振动问题。该文可供同行核电站管道专业设备维修及设备管理人员参考与借鉴。     

基于耦合程序的流体瞬变流动水锤现象分析

水锤现象严重威胁系统的安全,而设备的启闭是产生水锤现象的重要因素之一。本文针对并联双泵系统建立耦合程序,计算研究泵启动和阀门关闭时的流体瞬变水锤现象。验证过程证明了耦合程序的正确性,并将三维稳态模型计算结果与实验结果进行了对比,二者符合良好。瞬态分析中,动网格技术成功模拟阀门关闭,并获得了闭合时阀内的重要热工水力参数。通过对比泵启动耦合计算结果与传统RELAP5计算结果可知,耦合程序能正确预测水锤压力波和水锤载荷。耦合分析较一维计算能更直观地展现系统中重要设备内的流体瞬变特性。计算获得的三维瞬态特性能对阀门的设计和优化提供重要的参考。     

压水堆主管道双端断裂事故下管路系统的力和力矩分析

文章引入了国外采用的经验数据和公式，分析了其缺陷性，并从流体瞬变和流体力学理论出发对压水堆主管道双端断裂进行了分析和研究。先用特征线法求得回路系统在失水事故工况下的压力、流量变化曲线，再用控制体体积积分方法较为精确地计算出主管道的１１个断点分别断裂时，其他各点的受力和力矩。这些计算结果为压水堆核电站的核安全设计和分析提供了可靠保证     

水锤载荷作用下管道变形及动态应力

采用基于流构耦合的有限元方法模拟了管道内三维水锤现象发生的过程及管壁的动态响应。在考虑流体与管道结构体相互作用的基础上,通过任意拉格朗日欧拉法(ALE)仿真分析和确定了管壁最大变形发生在距管末端约1/3管径处,最大变形滞后于水锤波到达时刻。进一步研究发现,在管壁三维动态应力中,周向应力起主要作用,并且与水锤压力波的周期具有较强的相关性。     

铅铋介质闭式换向器运行特性与水锤现象研究

为研究闭式换向器在液态铅铋合金（LBE）介质换向过程中的流量稳定性及其适用性,采用FLUENT软件结合重叠网格方法对三通切换阀形式的闭式换向器换向时上游的压力与速度波动进行计算分析。结果显示,换向过程中,阀芯启动及停止运动时产生水锤,水锤波以介质声速在管道中传播,从而影响管道内压力和速度的分布,水锤波的峰值大小与介质密度、阀芯运动速度成正比,水锤波频率不受阀芯运动速度影响。由于水锤波的波峰值较大,使此类型闭式换向器在LBE下换向动作时上游管道难以维持稳定流量并威胁装置安全,故在LBE流量标定装置中不适用。     

美国核电站中的水锤及其评价

概括地总结了美国近年来对核电站中水锤事件的评价结果,包括水锤发生的原因,发生的频率,所造成的破坏和受影响的系统等。通过对水锤事件的评价以及根据以往核电站的运行经验,提出了防止、消除或者减轻水锤的一些设计上和运行操作方法上的改进措施,文中概括了当前美国NRC 对水锤问题的一些主要看法,并指出了水锤问题在我国核电站建设中的重要性。     

核电站输热管系中蒸汽泡溃灭模拟实验

管路热力输运系统中可能同时出现汽－液两相。当汽－液两相可能接触且存在温差时，会导致汽相急剧冷凝相变，引起蒸汽泡溃灭水锤，导致管系结构破坏。核电站中有大量布局十分复杂的热力输运管道，由于各种原因，蒸汽泡形成和溃灭极易发生。本文针对核电站热力输运管道中汽－液接触后蒸汽饱的形成条件以及溃灭造成的影响进行了分析，用摄影追踪流动显示方法再现了管道中流向发生急剧改变处被冷水隔离的高温蒸汽泡。由于急剧冷凝使得蒸汽体积急剧收缩，环绕的水体产生猛烈碰撞，并监测到该过程中局部压力所产生的瞬间峰值。由于水体对撞运动和逆压梯度，该过程会反复发生多次。利用VOF方法，计算模拟了二维管道系统中蒸汽泡形成的过程。核电站管路的设计和实际操作维护应及时诊断和避免上述问题的发生。     

Modelling the fluid structure interaction produced by a waterhammer during shutdown of high-pressure pumps

Measurements of an experiment in a pipe system with pump shutdown and valve closing have been performed in the nuclear power plant KRB II (Gundremmingen, Germany). Comparative calculations of fluid and structure including interaction show an excellent agreement with the measured results. Theory and implementation of the fluid structure interaction (FSI) and the results of the comparison are described. The following measurements have been compared with calculations: (1) experiments in Delft, Netherlands to analyse the FSI; and (2) experiment with pump shutdown and valve closing in the nuclear power plant KRB II has been performed. It turns out, that the consideration of the FSI is necessary for an exact calculation of ‘soft’ piping systems. It has significant application in current waterhammer problems. For example, water column closure, vapour collapse, check valve slamming continues to create waterhammers in the energy industry. An important consequence of the FSI is mostly a significant increase of the effective structural damping. This mitigates—so far in all KED’s calculations the FSI has taken into account—an amplification of pipe movements due to pressure waves in resonance with structural eigenvalues. To investigate the integrity of pipe systems pipe stresses are calculated. Taking FSI into account they are reduced by 10–40% in the actual case.     

核电厂蒸汽管道中水团冲击（水锤）的分析

蒸汽管道中夹带有水，可能会产生严重的水锤现象，以致造成管道或管道部件以及其约束件的损坏或丧失功能，对核电厂的安全运行是一个潜在的危害因素。提供了一种描述蒸汽管中水团的形成过程和水团对管道冲击力的计算方法，并给出了一个计算实例。     

Modal recovery methods for solution of fluid-structure problems with rigid wall loads

A method is presented which enables the acoustic modes of a fluid to be recovered in an analysis based on rigid wall loads of a structure or portion of a structure. It is shown that the method leads to a structural solution which is identical to the coupled fluid-structure solution provided that the fluid is discretized sufficiently to retain the requisite spectral fidelity. An application of this method to the waterhammer response of a pipe segment is given, which in addition to validating the method, shows that the coupled response differs significantly from the structural behavior predicted by added mass, or incompressible, representations of the fluid. When the method is used to recapture fluid-structure interaction in a subsystem, silent boundaries are needed for the fluid domain. The method is also applicable to many other fluid-structure problems, and is particularly useful when the fluid loads are determined experimentally or by complex computational methods that are not readily coupled with structural models.     

Use of spar elements to stimulate fluid acoustical effects and fluid-solid interaction in the finite element analysis of piping system dynamics

A technique is presented for using existing options in structural analysis finite element computer programs to simulate fluid acoustical effects and fluid-structure interaction in piping system dynamic analysis. With this technique, the fluid in straight pipe section is represented as a sequence of spar elements coupled to the pipe motion in the transverse direction but free to move independently in the axial direction. Special modeling considerations for treating the acoustical and fluid-structure interaction effects at elbows, tees and area changes are also derived. Results using this kind of modeling are presented for a pulse loading of a leg of piping with the same cross-sectional dimensions and elbow radii as the Clinch River Breeder Reactor Plant (CRBRP) primary piping.     

Response of piping system on friction support to bi-directional excitation

Installation of friction devices between a piping system and its supporting medium is an effective way of energy dissipation in the piping systems. In this paper, seismic effectiveness of friction type support for a piping system subjected to two horizontal components of earthquake motion is investigated. The interaction between the mobilized restoring forces of the friction support is duly considered. The non-linear behavior of the restoring forces of the support is modeled as an elastic-perfectly plastic system with a very high value of initial stiffness. Such an idealization avoids keeping track of transitional rules (as required in conventional modeling of friction systems) under arbitrary dynamic loading. The frictional forces mobilized at the friction support are assumed to be dependent on the sliding velocity and instantaneous normal force acting on the support. A detailed systematic procedure for analysis of piping systems supported on friction support considering the effects of bi-directional interaction of the frictional forces is presented. The proposed procedure is validated by comparing the analytical seismic responses of a spatial piping system supported on a friction support with the corresponding experimental results. The responses of the piping system and the frictional forces of the support are observed to be in close agreement with the experimental results validating the proposed analysis procedure. It was also observed that the friction supports are very effective in reducing the seismic response of piping systems. In order to investigate the effects of bi-directional interaction of the frictional forces, the seismic responses of the piping system are compared by considering and ignoring the interaction under few narrow-band and broad-band (real earthquake) ground motions. The bi-directional interaction of the frictional forces has significant effects on the response of piping system and should be included in the analysis of piping systems supported on friction supports. Further, it was also observed that the velocity dependence of the friction coefficient does not have noticeable effects on the peak responses of the piping system.     

Fluid dynamic interaction between water hammer and centrifugal pumps

Centrifugal pumps generate in piping systems noticeable pressure pulsations. In this paper the dynamic interaction between water hammer and pressure pulsations is presented. The experimental investigations were performed at a piping system with nominal diameter DN 100 (respectively NPS 4) and 75 m total length, built at the Institute for Process Technology and Machinery. Different measurements at this testing facility show that pulsating centrifugal pumps can damp pressure surges generated by fast valve closing. It is also shown that 1-dimensional fluid codes can be used to calculate this phenomenon. Furthermore it is presented that pressure surges pass centrifugal pumps almost unhindered, because they are hydraulic open.     

Precracked pipe under waterhammer action

We numerically simulate a full scale test in several computational steps with the finite element method and compare all calculated data with the experimental findings. First, we compute the deflection under static loading and the spectrum of eigenfrequencies of an integer piping, attached to a nuclear reactor pressure vessel (RPV). Then we consider a sudden pipe break at some distance from the vessel, immediately followed by an undamped closure of a check valve close to the break on the RPV side, and calculate the elastic and plastic transient dynamic response of the integer piping part between the RPV and the break. Finally, we consider a circumferential internal surface crack, fairly close to the vessel; after extensive testing of our fracture mechanics calculation procedure we investigate the stress in the crack region under the waterhammer action.     

Analysis of potential waterhammer at the Ignalina NPP using thermal–hydraulic and structural analysis codes

The RBMK (Russian acronym for ‘channeled large power reactor’)-1500 reactors at the Ignalina nuclear power plant (NPP) have a series of check valves in the main circulation circuit (MCC) that serve the coolant distribution in the fuel channels. In the case of a hypothetical guillotine break of pipelines upstream of the group distribution headers (GDH), the check valves and adjusted piping integrity is a key issue for the reactor safety during the rapid closure of check valve. An analysis of the waterhammer effect (i.e. the pressure pulse generated by the valves slamming closed) is needed. The thermal–hydraulic and structural analysis of waterhammer effects following the guillotine break of pipelines at the Ignalina NPP with RBMK-1500 reactors was conducted by employing the RELAP5 and PipePlus codes. Results of the analysis demonstrated that the maximum values of the pressure pulses generated by the check valve closure following the hypothetical accidents remain far below the value of pressure of the hydraulic tests, which are performed at the NPP and the risk of failure of the check valves or associated pipelines is low. Sensitivity analysis of pressure pulse dependencies on calculation time step and check valve closure time was performed. Results of RELAP5 calculations are benchmarked against waterhammer transient data obtained by employing structural mechanics code BOS fluids.     

Effect of plastic deformation of piping on fluid-transient propagation

A simple computational model is developed for incorporating the effect of elastic-plastic deformation of piping on pressure transient propagation in a fluid system. A computer program (PLWV) is described which incorporates this structural interaction model into a one-dimensional method-of-characteristics procedure for fluid hammer analysis. Computed results are shown to be in good agreement with available experimental data. The most significant effect of plastic deformation is to limit the peak pressure of a pulse leaving a pipe to approximately the yield pressure of the pipe, if the pipe is sufficiently long.     

A three-dimensional method for integrated transient analysis of reactor-piping systems

A three-dimensional method for integrated hydrodynamic, structural, and thermal analyses of reactor-piping systems is presented. The hydrodynamics are analyzed in a reference frame fixed to the piping and are treated with a two-dimensional Eulerian finite-difference technique. The structural responses are calculated with a three-dimensional co-rotational finite-element methodology. Interaction between fluid and structure is accounted for by iteratively enforcing the interface boundary conditions.A thermal transient capability has been developed. A system energy equation is used to compute the coolant temperatures due to convection. A radial heat-conduction equation is employed to establish the temperature profile throughout the pipe-wall thickness. The constitutive equation used for the thermal-mechanical stress calculation is suited for a large number of materials under various loading conditions, such as those having thermal, plastic, and viscous effects. The flow surface, which defined the purely elastic regime, can be arbitrarily small; an associated flow rule is utilized for regimes of material plasticity.Three sample problems are presented to illustrate this method. The first one calculates the piping response under the seismic excitation. The second one validates the heat-conduction model. The third problem deals with a coupled hydrodynamic-structural-thermal analysis of a piping system. Results are discussed in detail.