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。     

运动条件下铅铋反应堆热工水力特性研究

为研究运动条件下铅铋反应堆热工水力特性,开发了运动条件铅铋反应堆瞬态分析系统程序,并完成了对设计的5 MW自然循环小型模块化铅铋反应堆的建模,分析了运动条件对反应堆自然循环热工水力特性的影响。计算结果表明,倾斜条件下,堆芯流量减小,堆芯出口温度升高,在计算最大倾斜角度下,流量减小20%,冷却剂堆芯出口温度升高20 ℃。起伏条件下,起伏幅度和起伏周期越大,对反应堆影响越大,由于系统阻力影响,流量变化较起伏加速度有小于1 s的延时。摇摆条件下,摇摆角度越大和摇摆周期越小,对反应堆影响越大,燃料包壳峰值温度较稳态值高20 ℃以内,对反应堆正常运行时安全性影响较小。     

摇摆运动下多环路主冷却剂系统自然循环流量的稳定性分析

海洋核动力平台因其突出的安全性已成为当今核能领域热点研究问题之一,但在海洋等非惯性条件下会使一回路系统的热工特性发生变化。针对此问题,本文对几种典型的一回路系统在摇摆条件下的自然循环流量波动特性进行计算分析。分别建立典型的双环路、三环路、四环路的一回路系统模型布置方案,并同时考虑摇摆中心的位置,根据流体动量守恒方程,得到不同状态下一回路系统内的流量变化规律。对于单堆双环路系统,摇摆中心在船上/中/下部位置时,环路流量波动幅度分别为13.2%/11.2%/9.5%,堆芯流量波动幅度分别为0.9%/0.8%/0.6%;对于单堆三环路系统,摇摆中心在船下部时,环路流量和堆芯流量波动幅度分别为9.2%和0.8%;对于单堆四环路系统,摇摆中心在船下部时,布置方案1和方案2的环路流量波动幅度分别为9.5%和9.2%,堆芯流量波动幅度分别为0.9%和0.7%。计算结果表明：采用单堆双环路的设计布置方案是最有利于系统稳定性的。     

摇摆运动下多环路主冷却剂系统自然循环流量的稳定性分析

海洋核动力平台因其突出的安全性已成为当今核能领域热点研究问题之一,但在海洋等非惯性条件下会使一回路系统的热工特性发生变化。针对此问题,本文对几种典型的一回路系统在摇摆条件下的自然循环流量波动特性进行计算分析。分别建立典型的双环路、三环路、四环路的一回路系统模型布置方案,并同时考虑摇摆中心的位置,根据流体动量守恒方程,得到不同状态下一回路系统内的流量变化规律。对于单堆双环路系统,摇摆中心在船上/中/下部位置时,环路流量波动幅度分别为13.2%/11.2%/9.5%,堆芯流量波动幅度分别为0.9%/0.8%/0.6%;对于单堆三环路系统,摇摆中心在船下部时,环路流量和堆芯流量波动幅度分别为9.2%和0.8%;对于单堆四环路系统,摇摆中心在船下部时,布置方案1和方案2的环路流量波动幅度分别为9.5%和9.2%,堆芯流量波动幅度分别为0.9%和0.7%。计算结果表明:采用单堆双环路的设计布置方案是最有利于系统稳定性的。     

简谐海洋条件下自然循环运行特性

基于两相漂移流模型建立简谐海洋条件下核动力装置自然循环理论分析模型;采用两群三维时空中子动力学模型描述堆芯中子的物理行为及控制棒调节系统的响应;利用研制的程序对核动力装置在摇摆条件下的自然循环运行特性及强迫循环向自然循环转换的过渡过程进行研究.结果表明:摇摆周期越小,影响越大;摇摆振幅越大,影响越大;相同摇摆周期与摇摆振幅条件下,纵摇对自然循环运行影响大;纵摇时,参数波动周期与摇摆周期相符,横摇时,参数波动周期为摇摆周期的一半;海洋条件引起过大的堆芯自然循环流量波动可造成功率自动调节控制棒的频繁动作,无法平稳实现强迫循环向自然循环的转换.     

海洋运动对自然循环流动影响的理论分析

以一体化全功率自然循环反应堆模拟实验回路为物理原型,建立了非惯性系下自然循环流动理论分析模型。分别计算了稳态、横摇、纵摇、横倾、纵倾、起伏以及复合运动条件下满功率的自然循环流动,分析了附加惯性力对流体作用的机理。结果表明,摇摆附加惯性力引起各段流体波动,但不是导致堆芯流量波动的直接原因;起伏改变驱动压头大小,各段流量波动一致;倾斜工况下,不同空间位置的流道流量变化不同,堆芯流速下降。     

海洋条件下反应堆热工水力参数的子通道计算

针对海洋条件下反应堆的子通道热工水力分析,建立了海洋运动附加力模型和瞬态入口边界,将起伏、摇摆及复合运动的附加力关系式用于子通道模型的轴向和横向动量方程,并应用到COBRAⅢC程序将其改造为适应海洋条件的反应堆子通道分析程序。作为验证,计算了加热实验通道和"奥陆"堆在起伏运动情况下热通道的临界热流密度比(CHFR)、出口空泡份额和冷却剂流量,并与文献结果对比。还详细计算了"奥陆"堆在起伏、不同摇摆中心和复合运动情况下,热通道的CHFR和不同位置子通道出口的热工水力参数。研究表明:海洋条件下反应堆的子通道热工水力参数随运动呈周期性变化;起伏运动对子通道的压降影响较大,摇摆运动对子通道冷却剂的流量和温度影响较大。     

基于RELAP5的海洋条件下反应堆热工水力系统分析程序开发

研究了倾斜、起伏和摇摆等海洋条件的数学模型.通过修改控制方程,开发了国内首个基于先进的、自由节点划分的RELAP5程序,并且适用于海洋条件的反应堆热工水力系统分析程序RELAP5/MC.用RELAP5/MC对海洋条件下简单两环路系统的自然循环特性进行了计算,其结果都能得到合理解释,由此表明程序开发是初步成功的.     

海洋条件下压水堆单相自然循环无量纲分析

针对单相单环路自然循环系统,采用Boussinesq近似建立无量纲分析方程,通过对单相动量及能量守恒关系的推导,得到不同外界条件下自然循环流量的影响参数。分析讨论倾斜、起伏与摇摆因素对自然循环流量的影响,并给出单相自然循环运行流量约束的保持条件。研究表明,倾斜时单相自然循环流量随倾斜角度的增加而减少;起伏运动时如果加速度与重力加速度的比值较小,对自然循环的影响可忽略;在不同摇摆条件下,如果引起自然循环流量的振幅相同,则其最大摇摆角加速度必然相同;单相自然循环运行的流量约束数值可由热源过冷度条件获得。     

潜艇反应堆在摇摆运动中的自然循环和堆芯传热特性

在一个有摇摆运动的模型反应堆中进行了一系列的单相自然循环试验，以研究摇摆运动对其热工水力特性的影响。在每段管道中，流体由于摇摆运动的惯性力，流动速度随着摆动角度周期性地变化。当摇摆周期变短时环路流速振荡的幅度变大，摆动角度和环路流动速度振荡之间的相位差变大。另一方面，尽管堆芯的流速值随着摇摆周期变化，但是流速并不振荡。堆芯流速变化与摇摆运动的雷诺数和瑞利数密切相关，它是由热驱动头的变化和整个环路的压力损失的变化引起的。为了模拟堆芯流速随着摇摆速度的变化，建立了一个简单的一维分析模型，其正确性已被验证。由于摇摆运动产生局部流动，因此增强了堆芯中的传热。堆芯中的传热系数按摇摆运动的Richardson数的大小被分为三个区间。     

Natural circulation characteristics of a marine reactor in rolling motion and heat transfer in the core

A series of single-phase natural circulation tests in a model reactor with rolling motion was performed in order to investigate effects of the rolling motion on its thermal-hydraulic behavior. The loop flow rate in each leg changes cyclically with the rolling angle due to the inertial force of the rolling motion. As the rolling period becomes shorter, the amplitude of the loop flow rate oscillations becomes larger, and the phase lag between the rolling angle and loop flow rate oscillations becomes larger. On the other hand, the core flow rate does not oscillate, though its value changes with the rolling period. Its change correlates well with both the Reynolds number for rolling motion and the Rayleigh number, and it is considered to be caused by the change of the thermal driving head and the pressure loss through the loop. In order to simulate core flow rate change with the rolling period, a simple one-dimensional analytical model was proposed, and its verification was demonstrated. Heat transfer in the core is enhanced by the rolling motion and the enhancement is thought to be caused by the internal flow due to the rolling motion. Heat transfer coefficient in the core is well correlated with the Richardson number for rolling motion and is classified into three regimes.     

海洋条件下任意管道内附加压降的势函数分析和矢量代数积分方法

在海洋条件下,由于管道平移和摇摆运动会引入附加的体积力作用而产生附加压降。为了获得具有普遍适用性和便于应用的附加压降理论计算结果,从非惯性坐标系下流体动力学动量方程出发,将管道运动划分为平移和摇摆运动方式,应用流体力学势函数分析方法分别获得平移运动和摇摆运动离心力产生的附加压降计算关系式。根据附加压降物理定义,将管道摇摆运动划分为正交摇摆、平行摇摆2种基本方式,采用矢量代数积分方法获得摇摆运动切向力产生的附加压降计算关系式,并讨论了这些关系式的适用性。理论分析结果表明,海洋条件下任意管道内各项附加压降都可得到精确求解。     

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.     

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.     

摇摆条件下海上浮动堆全厂断电事故分析

为研究海洋条件对海上浮动堆全厂断电事故后的事故进程及非能动安全系统运行特性的影响,通过建立海洋条件加速度场模型,基于RELAP5程序开发获得了适用于海上浮动堆的系统分析程序,并对程序进行了实验验证。利用所开发的程序通过建立双环路海上浮动堆及二次侧非能动余热排出系统的计算模型,开展了不同摇摆运动参数下海上浮动堆全厂断电事故的计算分析。计算结果表明,船体的横摇运动可加快全厂断电事故后浮动堆系统压力和温度的下降速度,堆芯余热能够被二次侧非能动余热排出系统有效导出;但横摇运动会造成事故后堆芯自然循环流量的显著降低,引起一回路系统和非能动余热排出系统中自然循环流量的大幅度振荡及周期性倒流。本文计算结果可为海上浮动堆非能动安全系统的设计提供参考。     

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.     

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.