Flashing and flashing coupled density wave oscillation in natural circulation system

The phenomeon and mechainsm of different kinds of two-phase flow instabilities,namely geysering,flashing instability and flashing coupled density wave instability are firstly well interpreted by the experiment performed on the test loop(HRTL-5) simulating the 5-MW reactor.The flashing coupled density wave instability is analyzed by using an onedimensional non-thermoequilibrium two-phase flow drift model computer code.Calculation results are in good agreement with the experimetal.     

Effect of steam quality on two—phase flow in a netural circulation loop

Test pressures are 1.0-4.0MPa,heating powers 27-190kW,inlet subcoolings 5-80℃,water used as coolant,and steam quality at the outlet of test section is less than 0.05,These test conditions cover the parameters for a typical 200MW heating reactor.The experimental results show that the stema quality is the dominant factor in a natural circulation system with low pressure and low steam quality about the effect of system pressure,heating power and inlet subcooling on the flow rate,relative oscilatroy amplitude and oscilatory region of flow rate.     

Non-dimensional analysis of static bifurcation in a natural circulation loop

The steady-state characteristics of a two-phase natural circulation loop were investigated based on the homogenous model. Transcendental equations of non-dimensional loop mass flow rate under various conditions were also derived. The static bifurcation diagram of a two-phase natural circulation described with non-dimensional variables Npch-m^＋ was obtained. In addition, various steady-state characteristics of a natural circulation loop were analyzed and discussed. These characteristics include the existence of multiple solutions under certain conditions, and the maximum mass flow rate. The authors also examined the effects of important parameters such as sub-cooling number, riser-to-heated-region length ratio, and riser-to-heated-region diameter ratio.     

两相自然循环非线性特征及实验研究

采用均相模型,基于分岔理论预测了两相自然循环系统的流量漂移(静态分岔)相关特性,并对其进行了实验验证.同时,对系统的动态参数时序进行了时域和频域分析,研究了特定工况下沸腾喷发弛张动态不稳定性机理.通过对系统相关时序的相空间重构与分维分析,探讨了系统随加热功率变化的非线性演化规律.     

An analytical investigation of role of expansion tank in semi-closed two-phase natural circulation loop

Role of the expansion tank in a semi-closed two-phase natural circulation loop was examined analytically with the emphasis placed on the flow instability. Loopwise steady circulation rate was obtained, and conditions for flow instability were examined by using the method of the linear stability analysis with perturbations. The homogeneous two-phase model was adopted for the analysis. As well as the pressure at the expansion tank, the length and the cross-sectional area of the tube connected to the expansion tank appeared to be the important parameters determining the flow instability. The system was predicted to be stable with the longer length and the smaller cross-sectional area of the expansion-tank line and also with the higher expansion-tank pressure.     

两相自然循环非能动系统静态分岔特性和参数效应研究

耗散结构在流体动力学中存在,两相自然循环非能动系统稳定性是耗散结构在多相流体动力学中的问题,运用分岔理论及其DERPAR数值方法给出系统随参数变化的演化过程的静态分岔解图图谱。以静态分岔解图呈现的迟滞现象（多平衡解）定义了输热能力限、静态漂移稳定性准则、稳定性裕度、比质量流量输热能力、分岔现象消失—呈单值性的临界参数区的系统演化的自组织特性的物理本质—系统的稳态和时间相关态随着特征参数的演化。用低压下的实验数据与理论计算分析进行比较,变化趋势吻合,尚需进一步验证。     

Study on Pb-Bi natural circulation phenomena

For the development of 45w%Pb-55w%Bi cooled direct contact boiling water small fast reactor (PBWFR), experimental study on Pb-Bi-water direct contact boiling two-phase flow has been performed using Pb-Bi-water direct contact boiling two-phase flow loop. For stable start-up of the boiling flow operation, Pb-Bi single-phase natural circulation must be realized in a Pb-Bi flow system of the loop before water injection into Pb-Bi. The Pb-Bi flow system consists of a four-heater-pin bundle, a chimney, an upper plenum, a level meter tank, a cooler, and an electromagnetic flow meter. A stable Pb-Bi single-phase natural circulation was realized in the range of flow rate from 1.5 l/min to 4.8 l/min by heating Pb-Bi in the heater-pin bundle with a power up to 7.7 kW. The inlet and outlet temperatures of the heater bundle were in the ranges from 243°C to 278°C, and from 251°C to 278°C, respectively. The natural circulation flow was simulated analytically using one-dimensional flow model including frictional, form and drag forces. Total hydraulic head through the loop were calculated from Pb-Bi densities at measured Pb-Bi temperatures in the loop. It was found that the calculated flow rate agreed well with the measured ones, which indicated the validity of the analytical models.     

低干度自然循环两相流动系统的静态分岔特性

基于一维两相四方程漂移流模型，采用数值模拟的方法对5MW低温核供热堆热工模拟回路（HTRL-5）的自然循环进行模拟，分析在自然循环系统中存在的分岔特性及其参数效应。结果表明：在一定条件下低干度自然循环两相流动系统存在静态分岔现象，并且静态分岔点出现在特征曲线的切点上；当压力高到一定程度或热流密度小到一定程度系统的分岔点消失。     

Startup instability in natural circulation driven nuclear reactors

Natural circulation driven nuclear reactors are prone to flow instability during the startup transients. This paper intends to provide the state-of-the-art reviews on the theoretical analysis and experimental studies on flow instability in three types of natural circulation driven reactors, ranging from conventional nuclear reactors to small modular reactors. Brief overviews of three categories of startup flow instability, i.e., density wave oscillations, flashing instability, and Geysering instability, are provided. A critical review is conducted for the scaling analysis and design of small scaled test facility. The review of obtaining quasi-steady state stability maps in the dimensionless stability plane through frequency domain analysis and experimental tests provides the state-of-the-art methodology of analyzing the flow instability. Experimental startup instability during different initial startup procedures is reviewed. Although extensive efforts have been made to study the flow instability, further work is required to improve the scaling ability of experimental investigation and the accuracy of code analysis. Some discussions for future research directions are given.     

Effect of steam quality on two-phase flow in a natural circulation loop

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核动力装置强迫循环与自然循环过渡过程特性研究

针对某型压水堆核动力装置,建立反应堆及一回路系统强迫循环与自然循环的计算分析模型,并与试验值进行比较,验证了建立的模型计算精度高,满足工程分析的要求.利用建立的数学模型,对自然循环与强迫循环过渡过程进行分析计算,结果表明:强迫循环向自然循环转换过程中冷却剂流量、蒸汽发生器压力、反应堆出口温度是几个约束参数;自然循环向强迫循环的转换过程中反应堆功率变化与周期变化幅度较大.     

自然循环静态特性实验研究

介绍了在自然循环整体实验装置(NCIF)上完成的自然循环静态特性实验结果。通过对3种泵路(泵及其出口节流件)阻力系数条件下的自然循环静态特性实验,获得了一回路平均温度维持不变的自然循环工况下,系统各热工水力参数随加热功率的变化规律;并对影响稳态自然循环流动的主要因素进行了分析。