Mitigating check valve slamming and subsequentwater hammer events for PPFS using MOC

The method of characteristic (MOC) was adopted to analyze the check valve-induced water hammer behaviors for a Parallel Pumps Feedwater System (PPFS) during the alternate startup process. The motion of check valve disc was simulated using inertial valve model. Transient parameters including the pressure oscillation, local flow velocity and slamming of the check valve disc etc. have been obtained. The results showed that severe slamming between the valve disc and valve seat occurred during the alternate startup of parallel pumps. The induced maximum pressure vibration amplitude is up to 5.0 MPa. The scheme of appending a damping torque to slow down the check valve closing speed was also performed to mitigate of water hammer. It has been numerically approved to be an effective approach.     

核反应堆一回路系统水锤数值模拟

采用特征线法,针对核反应堆一回路系统特点建立完整的数学物理方程和边界条件。自主开发WAHAP水锤计算程序,并对含止回阀的4泵并联系统在启动及切换工况下的水锤特性进行模拟计算。计算结果表明,所研究工况中有2个不同阶段存在阀瓣多次剧烈撞击阀座的过程和2种形式的压差震荡。     

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。     

对冲式止回阀原理及启闭特性分析

压水堆核电站主泵工况变化时,由于止回阀阻止流体逆流,回路会发生程度不同的水击现象.水击严重时不但会产生瞬时超压,危害压力边界,也可能造成止回阀失效.对冲式止回阀是一种新原理止回阀,是为解决传统止回阀关闭时产生的严重水击现象而设计的.分析和实验表明对冲式止回阀能有效地解决回路的水击问题,也能可靠地阻止流体逆流.     

900 MW压水堆一回路系统水锤特性研究

针对压水堆水力过渡过程,建立了三环路900 MW压水堆一回路系统水锤完整的数理模型及边界条件。采用特征线法,开发了FORTRAN水锤仿真程序,并对三泵并联在启动和切换工况下的水锤特性进行了数值研究。研究发现启动和切换过程中,发生2次流量突变、流向逆转、压差突变和振荡;流量突变和逆转均发生在阀门关闭支路,呈振荡衰减的波动趋势,最大倒流流量达1 370 m3/h;压差突变发生在后启动支路,压差振荡最大值达40kPa;并联泵启动方式决定倒流流量和压差突变大小。     

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。     

对冲式止回阀局部流动特性仿真模拟

当压水堆核电站主泵工况变化时,回路会发生程度不同的水击现象,严重时不仅会产生瞬时超压危害压力边界,也可能造成止回阀失效。对冲式止回阀是一种新型止回阀,其新型的导流结构设计可很好地减轻水击现象,提高核电站运行的安全性。本工作基于FLUENT流体仿真软件,利用动网格及UDF(用户自定义函数)技术,更真实地模拟了阀门关闭过程中冲压管喉部及其联接腔体内的流场与压力分布。模拟结果表明,虽然几何形状的变化会导致关闭过程中局部流速高于其他部位的,但对阀门关闭过程的稳定性影响很小。另外,通过对流场分析发现,阀门关闭过程可分为3个阶段,每一阶段均有其独立特征,为以后阀门结构的改进及可靠性分析提供了依据。     

Analysis of the capability of system codes to model cavitation water hammers: Simulation of UMSICHT water hammer experiments with TRACE and RELAP5

The capabilities of the nuclear system transient codes TRACE and RELAP5 to model coupled two-phase flow and pressure wave propagations in a pipe are assessed by analyzing the UMSICHT PPP cavitation water hammer experiments 329 and 135 after valve closure. Time-dependent pressure, flow behaviour, and the generation and collapse of vapor bubbles at the valve and the first bridge are discussed. We show that both codes are able to model the flow behaviour of the water hammer for the high pressure and high temperature case 329 (initially 10–13 bar and 420 K), however condensation heat transfer for the base case needed to be increased in order to accurately model the magnitude of the first pressure excursion. The experimental broadening and damping of the subsequent pressure peaks by Fluid-Structure Interaction (FSI) phenomena arising from the interaction of the flow with the vibrations of the piping structure are not considered in the modeling results. For the lower pressure and temperature case 135 (initially 1–4 bar and 294 K), the TRACE code provides a good approximation of the propagation of the pressure wave and the void fraction behaviour, already with base case conditions, while RELAP5 overpredicts the vapor generation along the pipe and, as a result, considerably underpredicts the pressure amplitudes and overpredicts the water hammer frequency.     

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.     

核电厂主给水系统再循环阀设计布置试验研究

对某核电厂主给水系统再循环阀的设计布置进行试验研究,分析引起再循环管道在启泵瞬间突然跳动并伴随爆破声的根源,以及泵组基础错位及振动超标与再循环阀异常情况之间的关系。结果表明,多级笼式调节阀不能布置于有空气残留的高压给水管道中,否则在启动阶段将诱发破坏性水锤。通过优化再循环阀的设计布置,最终解决了主给水系统的非正常启动问题。      

Benchmarking analysis of water hammer effects using RELAP5 code and development of RBMK-1500 reactor main circulation circuit model

Correct prediction of water hammer transients is of paramount importance for the safe operation of the plant. Therefore, verification of computer codes capability to simulate water hammer type transients is a very important issue at performing safety analyses for nuclear power plants. Verification of RELAP5/MOD3.3 code capability to simulate water hammer type transients employing the experimental investigations is presented. Experience gained from benchmarking analyses has been used at development of the detail RELAP5 code RBMK-1500 model for simulation of water hammer effects in reactor main circulation circuit. In RBMK-type reactors the water hammers can occur in cases of rapid check valve operation. The performed analysis using RELAP5 code RBMK-1500 model has shown that in general the maximum values of the pressure pulses due to water hammer do not exceed the permissible loads on the pipelines.     

核岛重要厂用水系统停泵水锤计算分析

核岛重要厂用水（SEC）系统是核岛向最终热阱（大海）的直流海水输热系统、安全级系统,必须长期稳定、安全、可靠的运行。文章通过数值模拟的方法计算SEC系统停泵时的水锤过程,分析空气阀、单向调压水箱、缓闭止回阀水锤防护方案在SEC系统中的适用性。     

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.     

压水堆核电厂三回路停泵水锤数值模拟

应用停泵水锤的基本理论．建立了压水堆核电厂三回路水泵、泵出口阀、冷凝器和出水虹吸井等边界条件的数学模型．并采用特征线法进行求解结合工程实例计算说明．泵出口阀的关闭程序对水锤压力的影响较大．水泵出口采用两阶段关闭液控蝶阀可以有效减小停泵水锤压力．但其关闭程序应在水锤数值模拟分析的基础上优化确定。     

Flow-induced vibrations in closed side branch pipes and their attenuation methods

Some problems due to flow-induced vibrations related to closed side branch pipes have been observed in thermal and nuclear power plants. Fluctuating pressure generated in the main pipes was unusually, acoustically excited in closed side branch pipes, and intense vibrations were caused at pipes and components. For example, flow-excited acoustic resonance in closed side branches of stub pipes of safety relief valves caused the failure of steam dryers in the United States Quad City Unit 2 nuclear power plant. Furthermore, there was a possibility that residual air or gas in a closed side branch pipe unexpectedly caused severe vibrations of low frequency in the feed water piping system. We have investigated the root cause and influence of air on severe vibrations. Intense fluctuating pressure was often caused by water hammer due to valve closure and it became larger in the closed side branch pipes. We showed that an additional side branch with an orifice was very effective to suppress the flow-induced acoustic resonance. Design methods of the orifice to attenuate fluctuating pressure generated by water hammer were presented considering Mach number, the pressure loss coefficient of orifice and the intensity of particle velocity. Moreover, suitability of the characteristic curve method was confirmed for evaluation of the attenuation effect of an orifice on fluctuating pressure generated by water hammer. Finally, we considered some flow-induced vibration problems related to closed side branch pipes and their attenuation methods.     

反应堆管道系统水锤现象不利影响及防治措施研究进展

在核电反应堆及研究型反应堆系统中,水锤是一种较为常见的现象.反应堆循环水供水系统、蒸汽系统及其他辅助系统(如热阱)和水力测功系统等都曾发生过多起水锤现象.水锤现象往往伴随很响的锤击声,轻则引起相邻管道振动,重则导致结构性缺陷,造成管网漏液甚至供给中断,时刻威胁反应堆运行安全.本文调研了国内外水锤现象的研究现状及进展,重...     

Water hammer phenomena in a one-component two-phase bubbly flow

Water hammer phenomena caused by a rapid valve closure in a one-component two-phase bubbly flow were investigated experimentally. The experiments were conducted in a horizontal tube of 21.4 mm in inner diameter and 16.17 m long in ranges of superficial liquid velocity j_l from 0.5 to 1.5 m/s and of pressure from 0.25 to 1.5 MPa, using a refrigerant (R113), ethanol and water as the working fluid. The profiles of transient pressure, value of potential surge, and propagation velocity of the compression waves were obtained and discussed, comparing them with those in an air-water two-component two-phase flow. In particular, the pressure transient in a one-component two-phase flow is characterized by the existence of an exponential pressure decay just after the initial pressure rise. This phenomenon is closely related to the interface mass transfer.     

Hydrodynamic characterization and optimization of Contra-push check valve by numerical simulation

This paper introduced the structure and working principle of a new designed check valve, Contra-push check valve (CPCV), which can release water hammer and valve slam in accidents and special working status of nuclear power systems. The steady and transient characteristics of CPCV are simulated by CFD codes. Based on the experimental data, it is shown that the result is highly dependent on the turbulence model. The renormalization group theory (RNG) k–ε model is proved to be more accurate to describe the flow inside the valve. Steady hydraulic characteristics computed with RNG k–ε model agreed well with the experimental data at different positions of the plug. The Sensitivity analysis of structure parameters of CPCV were carried out in this study and two key factors were revealed.     

Direct contact condensation induced transition from stratified to slug flow

Selected condensation-induced water hammer experiments performed on PMK-2 device were numerically modelled with three-dimensional two-fluid models of computer codes NEPTUNE_CFD and CFX. Experimental setup consists of the horizontal pipe filled with the hot steam that is being slowly flooded with cold water. In most of the experimental cases, slow flooding of the pipe was abruptly interrupted by a strong slugging and water hammer, while in the selected experimental runs performed at higher initial pressures and temperatures that are analysed in the present work, the transition from the stratified into the slug flow was not accompanied by the water hammer pressure peak. That makes these cases more suitable tests for evaluation of the various condensation models in the horizontally stratified flows and puts them in the range of the available CFD (Computational Fluid Dynamics) codes. The key models for successful simulation appear to be the condensation model of the hot vapour on the cold liquid and the interfacial momentum transfer model. The surface renewal types of condensation correlations, developed for condensation in the stratified flows, were used in the simulations and were applied also in the regions of the slug flow. The “large interface” model for inter-phase momentum transfer model was compared to the bubble drag model. The CFD simulations quantitatively captured the main phenomena of the experiments, while the stochastic nature of the particular condensation-induced water hammer experiments did not allow detailed prediction of the time and position of the slug formation in the pipe. We have clearly shown that even the selected experiments without water hammer present a tough test for the applied CFD codes, while modelling of the water hammer pressure peaks in two-phase flow, being a strongly compressible flow phenomena, is beyond the capability of the current CFD codes.