摇摆条件下两环路自然循环回路特性分析

在海上小型堆设计中,需要考虑海洋运动条件对热工水力特性的影响。本文建立了海洋运动条件下的附加惯性力模型,并将该模型应用于RELAP/SCDAP程序中,得到了适用于海洋运动条件下的系统分析程序,利用修改后的RELAP5程序,分析了在摇摆条件下自然循环回路的热工水力特性。分析结果表明,摇摆条件下,自然循环回路的平均流量小于静止条件下的自然循环流量,环路流量波动滞后于横摇运动,冷却水温波动滞后于环路流量波动,摇摆幅值越大,频率越高,流量波动幅值越大。当摇摆较剧烈时,环路上出现倒流现象。增加加热功率或提高冷热源之间高度差可增加系统的自然循环驱动力,减小横摇运动对自然循环的影响。     

The influence of ocean conditions on thermal-hydraulic characteristics of a passive residual heat removal system

There are many differences between the flow and heat transfer characteristics of nuclear reactors under ocean and land-based conditions for the effects of ocean waves. In this paper, thermal hydraulic characteristics of a passive residual heat removal system (PRHRS) for an integrated pressurized water reactor (IPWR) in ocean environment were investigated theoretically. A series of reasonable theoretical models for a PRHRS in an IPWR were established. These models mainly include the core, once-through steam generator, nitrogen pressurizer, main coolant pump, flow and heat transfer and ocean motion models. The flow and heat transfer models are suitable for the core with plate-type fuel element and the once-through steam generator with annular channel, respectively. A transient analysis code in FORTRAN 90 format has been developed to analyze the thermal–hydraulic characteristics of the PRHRS under ocean conditions. The code was implemented to analyze the effects of different ocean motions on the transient thermal-hydraulic characteristics of PRHRS. It is found that the oscillating amplitudes and periods of the system parameters are determined by those of the ocean motions. The effect of rolling motion is more obvious than that of pitching motion when the amplitudes and periods of rolling and pitching motions are the same. The obtained analysis results are significant to the improvement design of the PRHRS and the safety operation of the IPWR.     

一体化压水堆强迫循环转自然循环过渡过程特性分析

针对一体化压水堆核动力装置,以核动力装置瞬态最佳估算程序RELAP5/MOD3为基础,采用两群三维时空中子动力学模型替代点堆模型,并建立三维空间内中子物理与热工水力的耦合模型,研制相应的计算程序。对一体化核动力装置强迫循环向自然循环转换过程进行仿真模拟。在过渡过程中,一体化压水堆核动力装置反应堆功率变化幅度较大,冷却剂流量的变化对一回路温度影响较大。     

Experimental study on two-phase flow instability of natural circulation under rolling motion condition

Two-phase flow instability of natural circulation under a rolling motion condition is experimentally studied. The experimental results show the rolling motion induces a fluid flow fluctuation. At the trough point of the flow fluctuation, rolling motion can cause the early occurrence of natural circulation two-phase flow instability, and this case is defined as trough-type flow oscillation. The system stability decreases with increasing rolling amplitude and effect of rolling frequency is nonlinear. The complex overlap effect of trough-type flow oscillation and density wave oscillation can enhance the system coolant fluctuation; this case is defined as complex flow oscillation. Complex flow oscillation may be divided into two types: regular and irregular complex flow oscillations. Irregular complex flow oscillation is a transition type from trough-type flow oscillation to regular complex flow oscillation. Under the same thermal hydraulic conditions, the marginal stability boundary (MSB) of regular complex flow oscillation is similar to that of density wave oscillation without rolling motion, and the influences of rolling parameters on the MSB are slight.     

摇摆运动下单相自然循环核热耦合特性研究

采用考虑6组缓发中子的点堆中子动力学模型,开发了核反馈模拟模块,并将之与摇摆条件下单相自然循环热工水力计算模型进行合并,基于Matlab软件编制了相应的计算程序,实现了摇摆条件下单相自然循环核热耦合的模拟计算。计算结果表明：摇摆条件下,与不考虑核反馈相比,考虑核反馈后核热耦合效应使系统流量降低,系统功率产生波动;系统功率的平均值随摇摆频率及振幅的增大而降低,而系统功率的振幅则随摇摆周期及振幅的增大而增大。核热耦合效应使燃料元件温度的波动振幅减小,起到了抑制燃料温度波动的作用。     

Flow characteristic of single-phase natural circulation under ocean motions

Natural circulation is widely used in nuclear reactor systems as the passive safety system. With the development of the floating nuclear power plant (FNPP), researchers should pay more attention to flow and heat transfer characteristics for the natural circulation under ocean conditions for the safety of FNPP. In this paper, the flow characteristics in a single-phase natural circulation system were investigated and the effects of heaving, rolling and coupled motions were analyzed. The oscillation amplitude of flow rate increases with the increase of period in a certain range and maximum acceleration under heaving motions. With the increase of oscillation intensity (higher frequency and larger maximum rolling angle), the oscillation amplitude increases and the average flow rate decreases under rolling motions. Moreover, the lateral displacement of rolling center changes the oscillation period and induces larger amplitude oscillations. The flow characteristic becomes more complex when the system is subjected to coupled motions. The oscillation period is the least common multiple of two motions’ periods. The oscillation induced by coupled motions makes the system more unstable than that induced by an individual motion. The potential superposition effect exists under coupled motions and needs to be addressed for the operation safety.     

The development and validation of a thermal hydraulic code in rolling motion

An advanced thermal hydraulic code is established on the basis of RELAP5/MOD3.3 code for the investigation of the thermal hydraulic behavior of nuclear power systems. The RELAP5 code is modified by adding a module calculating the effect of rolling motion and introducing new flow and heat transfer models. The experimental data are used to validate the theoretical models and calculation results. It is shown that the advanced flow and heat transfer models could correctly predict the frictional resistance and heat transfer coefficients in rolling motion. The thermal hydraulic code is used to simulate the operation of a natural circulation system in rolling motion. The calculation results are in good agreement with experimental data. The relative discrepancies between calculation results and experimental data are less than 5%.     

CFD analysis of flow and heat transfer of turbulent pulsating flow in a tube in rolling motion

The investigation of flow and heat transfer of turbulent pulsating flow is of vital importance to the nuclear reactor thermal hydraulic analysis in ocean environment. In this paper, the flow and heat transfer of turbulent pulsating flow is analyzed. The calculation results are firstly verified with experimental data. The agreement between them is satisfactory. The effect of spanwise and wall-normal additional forces is significant in small Reynolds number, and decreases with Reynolds number increasing. The rolling axis and rolling radius contribute slight to the flow and heat transfer. The effect of velocity oscillation period on the heat transfer is limited than that of Reynolds number and oscillating velocity Reynolds number. The traditional empirical correlations could not predict the flow and heat transfer of turbulent pulsating flow in rolling motion.     

Experimental investigation of natural circulation in a symmetrical loop under large scale rolling motion conditions

In ocean environment, the ship motion significantly affects the natural circulation behavior in ship-based integrated-type reactor. This paper theoretically and experimentally investigated natural circulation characteristics in symmetrical loops under rolling condition. Experiments were carried out on a test loop with a symmetrical configuration by simulating the structure of an accrual reactor. The theoretical results revealed that only angular acceleration contributes to the resultant force under zero power rolling condition. In a closed circuit with a uniform cross-section area, the angular acceleration force integral is proportional to the angular acceleration and the area enclosed by the circuit. The integral value varies over time and causes flow oscillations. However, the angular acceleration force does not influence the flow status in the shared part of the two symmetrical neighbor circuits due to force interactions. Rolling experiments with a zero power load confirmed these results. Full power experiments under rolling condition exhibited observable flow rate and temperature oscillations in each branch of the flow channel. The oscillations in the side flow channels had the same values for both the period and the phase with the variation of rolling angle. The angular acceleration force was the main cause of this. The oscillations in the middle channel had a period half the value of the rolling period. The periodical variation of the vertical component of gravity caused this. The horizontal component of gravity was out-phasing with angular acceleration. Therefore, it alleviated oscillation in the side channels. The experimental results showed that for the same rolling period, as the rolling angle increased, the average flow rate decreased and oscillation amplitudes increased. Also, as the power load increased, the oscillations in the middle channel increased and the oscillation in the side channel decreased.     

摇摆运动下单相自然循环流动特点

针对摇摆工况下单相自然循环流动的特点进行实验研究。实验结果表明,流体在摇摆作用下产生波动;波动频率与摇摆频率一致。理论分析表明,摇摆对自然循环的影响主要有两个方面,一方面摇摆引起回路空间位置的改变导致自然循环驱动压头发生变化;另一方面,摇摆引起的附加加速度使回路产生附加压降。通过建立简化模型,得出了摇摆周期、摇摆振幅和其他参数对单相自然循环流动影响的规律。     

摇摆运动对自然循环流动不稳定性的影响

分析研究了摇摆运动下的自然循环流动不稳定性和摇摆对不稳定性的类型以及不稳定性起始点的影响.结果表明,摇摆使流动不稳定性提前发生,改变了不稳定性的类型,摇摆引起的波动和密度波型脉动发生叠加.摇摆运动下自然循环存在两个稳定区域,在这两个区域中间包含着不稳定区域.     

摇摆对非能动余热排出系统自然循环能力影响的试验研究

在摇摆台架上对摇摆条件下的非能动余热排出系统的自然循环能力及其相关特性进行了试验研究。分析了附加压降和重位压降对流动特性的影响,以及摇摆条件下的重位压降和流动阻力对流速的影响。结果表明:摇摆条件下,非能动余热排出系统自然循环能力下降。摇摆振幅越大,平均凝水流量越小,波动幅度越大;凝水流量最小值随摇摆振幅的增大而下降很多,但凝水流量最大值变化较小。系统参数变化与摇摆周期关系不大。附加压降不会对平均流速产生影响,重位压降对平均流速的影响与周期无关。重位压降对流速的影响比流动阻力的影响小得多。随着摇摆振幅的增加,流动阻力对平均流速的影响略有降低。     

Unsteady Reynolds Averaged Navier–Stokes simulation of the turbulent flow pulsation and coherent structures in a tight lattice in rolling motion

The flow in a tight lattice is strongly affected by the quasi-periodic lateral flow pulsations caused by large scale vortices. This kind of large scale vortices is largely responsible for the momentum and heat exchange across the gaps. In rolling motion, the coherent structure and flow oscillation are affected by an additional force. The coherent structure in rolling motion is more significant than that in no rolling motion. The oscillation period in rolling motion is about 10% bigger than that in no rolling motion. The rolling motion can affect the coherent structure. However, the effect of rolling motion on the thermal hydraulic parameters, i.e. wall temperature and bulk temperature, is very limited. The wall temperature and wall shear stress in rolling motion and no rolling motion are nearly the same. The additional force due to rolling motion can change the moving characteristics of coherent structures, but its effect on the turbulent flow and heat transfer is weak.     

静止和摇摆条件下浮动式核电站一二回路PRHRS特性分析

浮动式核电站长期在海洋环境中运行,各系统都会受到海洋运动条件的影响。非能动余热排出系统（PRHRS）可在核电站发生全厂断电事故的情况下带出堆芯衰变余热,防止堆芯熔化,是重要的反应堆辅助系统。本文以一种采用海水作为最终热阱的浮动式核电站作为研究对象,分别设计了一回路和二回路PRHRS,开展了静止和摇摆条件下反应堆系统发生全厂断电事故的计算,对两种PRHRS在静止和摇摆条件下的运行特性进行了分析。研究表明,静止条件二回路PRHRS具有更强的带热能力,摇摆条件下一回路PRHRS的带热能力更加稳定。     

Numerical analysis of flowing characteristics of turbulent flow in rectangular channels in ocean environment

Because of the periodic effects of ocean waves, there are great discrepancies between the operational characteristics of nuclear power systems in ocean environment and that of land-based nuclear power systems. In some special operational status, like natural circulation, the additional forces due to ocean environment may impose so great disturbance on the coolant flow that theatres the safety operation of the systems. In the present paper, the turbulent flow in rectangular channels in ocean environments is investigated theoretically with CFD code FLUENT. The effects of several parameters on turbulent flow are analyzed. The effects of rolling motion includes two parts, the first part is the additional force parallel to flowing direction, which can affect on the pressure drop of the flow and change the flowing velocity, and the other part is the additional force perpendicular to flowing direction. In ocean environments, the flowing characteristics of turbulent flow are dominated by the additional force parallel to flowing direction. The effect of additional force perpendicular to flowing direction is very limited. In rolling and heaving motions, if the flowing velocity is the same, the flowing characteristics of turbulent flow are nearly the same, too. The bigger the Reynolds number is, the more serious the oscillation of turbulent kinetic energy and frictional resistance coefficient is, and the more the oscillation of turbulent flow is. The relationship between average frictional resistance coefficient and velocity oscillating amplitude is quadratic. And the oscillating amplitude of frictional resistance coefficient is in direct ratio with velocity oscillating amplitude.     

摇摆条件下热工水力程序的研制与验证

在RELAP5/MOD3.3程序的基础上,通过添加计算摇摆因素的模块和引入新的流动传热模型以对原程序进行修正,从而建立了摇摆条件下的热工水力分析程序。利用实验结果对理论模型和程序计算结果进行了校核和验证。结果表明：本文采用的流动传热模型可准确计算出摇摆条件下的摩擦阻力系数和传热系数,建立的热工水力分析程序也可对摇摆条件下的热工水力系统进行模拟。     

摇摆条件下自然循环流动不稳定性的混沌特性研究

对摇摆条件下两相自然循环系统不规则复合型脉动进行了非线性时序分析。通过相空间重构计算了不规则复合型脉动时间序列的关联维、K₂熵和最大Lyapunov指数值,在几何不变量的计算结果基础上,结合密度波型脉动和波谷型脉动的对比,分析了不规则复合型脉动的混沌特征和产生机理。分析结果表明：不规则复合型脉动为典型的混沌运动,热驱动力、流动阻力和摇摆引起的附加外力的相互作用和耦合导致了混沌的出现。     

Thermal-hydraulic behavior of a marine reactor during oscillations

The effect of ship motion, such as heaving and rolling, on the thermal-hydraulic behavior of marine reactors was investigated. The COBRA-IV-I CODE was modified to analyse the thermal-hydraulic performance on the critical heat flux under oscillating acceleration conditions. The critical heat flux in the code was verified experimentally using freon as a comparison. The Critical Heat Flux Ratio (CHFR) at the hottest channel of the PWR subchannel was analysed using the same code. A system code RETRAN-02/MOD2-GRAV was developed by improving RETRAN-02/MOD2 to simulate the thermal hydraulic transient under ship motion. It was verified by comparison using the experimental results of both two-phase natural circulation flow under heaving motion and single-phase natural circulation flow at an inclined attitude. The code was used to analyse reactor plant behavior in the nuclear ship Mutsu. Natural circulation flow during rolling motion was investigated experimentally. The characteristics of loop flow and core flow rates were clarified. The core flow rate correlated well with the Reynolds number of rolling motion.     

采用FFT方法对横摇条件下堆芯核热耦合流动不稳定性的分析

基于开发的海洋条件下堆芯核热耦合流动不稳定性分析程序,利用快速傅里叶变换（FFT）方法对堆芯通道的流量振荡曲线进行分析,获得了静止和横摇条件下堆芯发生核热耦合流动不稳定性时通道的频谱特性。研究表明,静止条件下堆芯发生流动不稳定性时仅具有1个频率峰值,其对应固有频率;在横摇条件下堆芯发生流动不稳定性时,堆芯所有通道均受到横摇条件和核热耦合效应影响,但只有最高功率通道中固有频率处于支配地位,该类功率通道首先发生流动不稳定性。FFT方法可精确地分析复杂流量振荡曲线的特性,进而判定横摇下堆芯核热耦合系统是否发生流动不稳定性。     

摇摆对自然循环核热耦合平均功率的影响

通过对摇摆条件下单相自然循环核热耦合的模拟计算,分析研究了摇摆条件下自然循环核热耦合系统平均功率的影响因素。分析结果表明：摇摆条件下,考虑核反馈后的系统平均功率与系统的平均质量流量、系统的平均传热系数成正比,与慢化剂与燃料的温度反馈系数比成反比。摇摆参数对系统平均功率的影响和慢化剂与燃料的温度反馈系数比有关。当系统平均传热系数的变化对反应性的影响起主导作用时,摇摆越剧烈,系统平均功率越大;当平均阻力系数的变化对反应性的影响起主导作用时,摇摆越剧烈,系统平均功率越小。