1000 MW核主泵失水事故工况下气液两相流分析

针对1 000 MW压水堆核电站主泵水力性能要求,在对核主泵进行水力设计和三维造型的基础上,采用CFD技术对失水事故工况核主泵气液两相流进行数值计算,并分析了失水事故工况下的核主泵气体分布,不同空泡份额工况下气体在流道内变化,以及空泡份额、冷却剂温度对核主泵扬程、效率的影响。计算结果表明：事故工况核主泵叶轮内气体主要分布在叶轮轮毂附近区域;沿叶轮轴向方向含气量逐渐增高,而沿径向方向含气量逐渐降低;当空泡份额在15%范围内,随着空泡份额的增加,扬程由113 m降低到85 m,效率由75%下降到65%,但仍能正常工作;当空泡份额大于15%,泵性能急剧下降,扬程下降到48 m,效率也降低到31%,泵丧失正常工作能力;冷却剂温度在270～350 ℃范围内,随着冷却剂温度增加,效率、扬程变化很小,但当温度超过350 ℃,主泵的性能急剧下降,致使主泵无法安全运行。     

强迫对流沸腾模型中的分布参数C0的新计算公式

强制对流沸腾在能源和加工工业中占有重要地位，在核电站中尤其重要。对于不同类型的压水堆，在启动过程、正常或者事故工况下冷却剂在管道内可能发生沸腾。粗略估计，此时的空泡份额甚至能达到0．9。本研究的目的是研究在上述热工水力条件下的两相流动模型。根据法国原子能委员会（CEA）在格勒诺布尔的氟里昂12（R12）回路上得到的实验数据发现，在大空泡份额情况下，流动特性近似于起泡的乳状液。此时，无论空泡份额多大，液相都保持连续的状态。在此结论基础上，我们为漂移流模型中的分布参数C0建立了一个新的求解模型，用低过冷、低空泡份额情况下R12回路的数据对该模型进行了校验，结果表明与高空泡份额下R12以及高压矩形通道内流体的沸腾实验数据非常吻合。     

主泵两相降级对大破口失水事故的影响研究

大破口失水事故过程中,主泵的工作范围覆盖了单相液、气液两相和单相气工况。在两相工况下,主泵的扬程和转矩发生降级。对于AP1000核电厂,WCOBRA/TRAC被用于大破口失水事故分析,其现有的主泵两相降级数据来源于西屋W93A主泵。为正确模拟AP1000主泵在大破口失水事故过程中的热工水力特性,需对其两相降级特性进行研究。本研究分别采用国际上广泛使用的SEMISCALE和EPRI/CE主泵的两相降级数据进行AP1000冷段双端断裂事故的计算分析,并与原有W93A的计算结果进行对比。结果表明,AP1000主泵两相降级特性对反应堆冷却剂系统压力、破口流量和安注箱流量影响不大。相比于SEMISCALE和EPRI/CE,现有的W93A的两相降级数据将导致更低的堆芯冷却流量和更高的包壳峰值温度最大值,计算结果相对偏于保守。     

核主泵水力性能数值预测的缩比效应研究

为提高核主泵的整体水力性能,实现与屏蔽电机的最优匹配,基于缩比模型换算法,选取RNGk-ε湍流模型和SIMPLEC算法,对核主泵进行非定常数值预测及外特性试验。结果表明:在0.4Qd~0.7Qd流量工况下,扬程-流量曲线较为平坦;额定工况下,扬程预测值较额定值高5%,叶轮扬程最大值在0.4Qd工况点,水力效率最大值在0.9Qd工况点,叶轮水力效率模拟值较试验值高5%;小流量工况下,导叶水力损失呈以0.4Qd工况点为中轴线的正态分布,水力损失最大值在0.4Qd工况点;大流量工况下,导叶水力损失最小值在1.1Qd工况点。压水室水力损失符合正弦波分布规律,波峰在0.4Qd工况点附近,波谷在0.9Qd工况点附近。     

气液两相流工况下核主泵的正转全特性研究

在冷却液流失事故(LOCA)事故发生期间,核主泵将处于两相混合运行状态。主要对核主泵的正转全工况不同含气率冷却介质的泵水力性能、流道内部气体体积分布情况及流体流态进行研究,并采用计算流体力学(CFD)模拟计算与气液两相流试验进行验证。研究发现:在正转逆流制动工况,核主泵的扬程曲线随含气率增加整体向下偏移,但其变化规律基本相同。在正转水泵工况和正转正流制动工况,随着流量增加,含气率对核主泵扬程特性的影响逐渐减小,且同流量下核主泵的扭矩和冷却剂介质密度成较为明显的正比关系。     

自然循环过冷沸腾截面平均空泡份额实验与计算方法研究

采用RBI高温高压光学探针,对自然循环过冷沸腾截面平均空泡份额进行了实验研究通过实验数据与应用较为普遍的Saha模型、Levy模型以及孙奇提出的真实质量含汽率模型计算值的比较发现．基于强迫循环实验数据的截面平均空泡份额计算模型无法适用于自然循环工况,且经过比较初步判定相同系统参数下高过冷沸腾区自然循环较强迫循环空泡份额偏高,另外,根据模型的比较分析结果对真实质量含汽率模型进行了拓展,使其可适用于自然循环过冷沸腾工况。     

基于激光诱导荧光法的空泡份额测量

激光诱导荧光技术作为可视化实验领域中的新技术,在核反应堆热工水力研究中得到了越来越广泛的运用。将激光诱导荧光技术应用于气液两相流空泡份额的测量中,介绍了激光诱导荧光法测量空泡份额的原理,描述了激光诱导荧光法测量空泡份额的具体实施方法,说明了图像数据的处理方法,并将该测量空泡份额方法用于气液两相流实验测量研究,在不同工况下进行了竖直通道内两相流空泡份额测量实验。实验结果表明,利用激光诱导荧光技术测得的空泡份额与理论预测结果符合较好。运用该方法能对流场内的空泡份额分布进行连续测量,且不会对流场造成干扰。     

气动式脉冲液体射流泵性能实验研究

实验研究了喷嘴直径为5 mm,扩散管直径分别为5、7 mm,提升高度为6.7 m的气动式脉冲液体射流泵的性能。结果表明:料桶内的液面高度对气动式脉冲液体射流泵的效率、扬程、输送量影响甚微,而随着操作压力的增加,脉冲液体射流泵的效率、扬程、输送量也增大。证明了在本实验条件下,最佳喷嘴间距与喷嘴直径之比为0.8～2.0范围内,并讨论了不同喷嘴间距所对应的最低操作压力条件。     

振动幅度对两相流局部参数变化影响研究

为研究实验段振动对管内两相流局部参数变化的影响,利用电导探针技术对振动状态下局部两相流特性参数包括空泡份额、气泡直径和界面浓度进行了测量。实验首先在静态工况下进行,通过固定在实验段上方的偏心轮转动获得振动工况。实验段振动周期保持在0.5 s,偏心轮提供的振动幅度分别为4.8 mm、9.5mm和15.8 mm。实验结果表明,振动对环管内气-水两相流局部时均参数分布影响很小。但振动引起的附加惯性力作用使两相流局部参数径向分布在实验段振动周期中发生明显变化,而且局部参数的变化幅度随实验段振幅的增加而显著增大。在含气率较低的流动工况,当振幅增大到15.9 mm时振动工况下径向空泡份额峰值较静态工况下的空泡份额峰值的增量可以达到70%。但振动对局部流动参数的影响随气流量增大而降低。     

倾斜圆管内泡状流空泡份额特性实验研究

采用光纤探针测量方法对倾斜圆管(内径为50 mm)内空气-水两相泡状流空泡份额分布特性进行实验研究。结果表明,截面平均空泡份额随倾斜角度的增加而减小,倾斜角度大于5°时减小速率明显减慢;竖直条件下空泡份额径向分布呈"马鞍形",即空泡份额除在近壁区出现峰值然后迅速降低到最小值外,在其他区域几乎不随位置发生变化;倾斜条件下气泡明显向上壁面聚集,中心线上方近壁区空泡份额峰值增加,中心线下方近壁区空泡份额峰值被削弱,倾斜角度较大时甚至消失。     

Effect of compensation error in drift-flux parameters on predictions of thermal-hydraulic parameters in nuclear safety system analysis codes

Void fraction in a nuclear reactor core is one of the most important parameters in a safety analysis using nuclear reactor thermal-hydraulics system analysis codes such as TRAC-BF1, RELAP5 and TRACE. Interfacial shear term governing void fraction in the two-fluid code is often estimated by Andersen approach which uses drift-flux type correlation to compute the interfacial shear term. The accuracy of two drift-flux parameters such as distribution parameter and drift velocity is anticipated to affect the accuracy of predicted void fraction significantly. In principle, the distribution parameter and drift velocity are independent parameters which should be determined by local gas and liquid velocities and void fraction. However, due to very limited local data, the distribution parameter and drift velocity are commonly determined by area-averaged void fraction and superficial gas and liquid velocities. This “approximate method” is acceptable when the distribution parameter and drift velocity are used together. However, in the Anderson's approach, the distribution parameter and drift velocity determined by the approximate method are used separately which may cause some compensation error in code calculations. In view of the great importance in accurately computing the interfacial shear term, the effect of the compensation error on the predicted void fraction is investigated. Intensive sensitivity analysis suggests the compensation error propagating to void fraction only up to 1% for steady state computations, whereas the effect of the compensation error on the predicted void fraction for transient computations becomes larger because temporal reduction of drag force may cause the increase in void fraction. A prototypic nuclear power plant analysis for ATWS scenario suggests that the overestimation of the void fraction may affect the neutron flux calculation.     

Evaluation of Delayed Neutron Fraction β for Thermal Fission of U-235 Based on Integral Experiments Using SHE

Countercurrent gas-liquid flow is theoretically and experimentally evaluated for a boiling system simulating a BWR core. In a single channel, flow patterns are determined from the mass balance equations and pressure drop under steady state conditions is calculated for each flow pattern using a drift flux model, where the distribution parameter and drift velocity are correlated as functions of void fraction and hydraulic diameter from void fraction data. The calculated pressure drop shows a similar trend to that of the data for the effects of bypass leak flow rate and heater power. Countercurrent behavior in three boiling channels under slow transient conditions is also predicted from the single channel characteristics and close agreement is obtained between the predicted and experimental results. The results show that steam up-flow or cocurrent up-flow easily occurs in a channel with low pressure drop, namely, with a large entry orifice, high power or low bypass leak flow rate.     

Two-Phase Flow Phenomena in Broken Recirculation Line of BWR

When a primary recirculation line of BWR is ruptured, a primary recirculation pump may be subjected to very high velocity two-phase flow and its speed may be accelerated by this flow. It is important for safety evaluation to estimate the pump behavior during blowdown. There are two problems involved in analyzing this behavior. One problem concerns the pump characteristics under two-phase flow. The other involves the two-phase conditions at the pump inlet. If the rupture occurs at a suction side of the pump, choking is considered to occur at a broken jet pump nozzle. Then, a void fraction becomes larger downstream from the jet pump nozzle and volumetric flow through the pump will be very high. However, there is little experimental data available on two-phase flow downstream from a choking plane. Blowdown tests were performed using a simulated broken recirculation line and measured data were analyzed by TRAC-PIA. Analytical results agreed with measured data.     

基于竖直圆管空气-水两相流实验的相间曳力模型研究

研究两相流相间阻力特性对系统程序关键本构模型封闭具有重要意义。本文基于竖直圆管开展了空气-水两相流实验,采用四探头电导探针对空泡份额、气泡弦长和界面面积浓度等气泡参数的径向分布进行了测量。结果表明空泡份额和气泡弦长呈现“核峰型”分布,而界面面积浓度并没有表现出随流速的单调关系。进一步开发了泡状流和弹状流的相间曳力模型,考虑了液相表观流速与管径对气泡尺寸分布的影响,建立了临界韦伯数与不同液相流速的关系。计算得到的空泡份额和界面面积浓度与实验数据整体符合较好,验证了模型的可靠性,为两相流相间阻力特性研究提供参考意义。     

The effect of turbulent mixing models on the predictions of subchannel codes

In this paper, the predictions of the COBRA-IV and ASSERT-4 subchannel codes have been compared with experimental data on void fraction, mass flow rate, and pressure drop obtained for two interconnected subchannels. COBRA-IV is based on a one-dimensional separated flow model with the turbulent intersubchannel mixing formulated as an extension of the single-phase mixing model, i.e. fluctuating equal mass exchange. ASSERT-4 is based on a drift flux model with the turbulent mixing modelled by assuming an exchange of equal volumes with different densities thus allowing a net fluctuating transverse mass flux from one subchannel to the other. This feature is implemented in the constitutive relationship for the relative velocity required by the conservation equations. It is observed that the predictions of ASSERT-4 follow the experimental trends better than COBRA-IV; therefore the approach of equal volume exchange constitutes an improvement over that of the equal mass exchange.     

Influence or Void and Flow Regime on Liquid Metal MHD Induction Generator Using Two-Phase Flow

In the present paper, the performance characteristics of a liquid metal MHD induction converter operated with two-phase mixture flow are treated experimentally and analytically in comparison with those with single-phase liquid flow as working fluid.

The experiments were performed with a flat-linear channel induction converter, through which NaK-N₂ two-phase mixture was made to flow at a velocity ranging 5–30m/sec, with a void fraction 0–50%.

Data were taken over the following range of non-dimensional parameters:

• Reynolds number: 3.3x10⁴–2.0x10⁵ (for liquid flow alone)

• Hartmann number: 12 (with magnetic field in r.m.s. and slip S = 1)

• Baroczy's property index: 0.0031–0.023 (for two-phase flow)

The electrical power output of the experimental generator showed a sudden decrease near 20% void fraction, which was attributed to change in the flow pattern, while the generator efficiency did not show such an abrupt drop, but decreased gradually with increase of the void fraction.

Coupling the electro-magnetic equations with the power law distribution for both fluid velocity and void fraction proposed by Bankoff, we have obtained numerically the performance characteristics of the liquid metal MHD induction converter operated with two-phase flow, which provided a quite satisfactory clarification of the results obtained experimentally.     

Validation of the sub-channel code F-COBRA-TF: Part II. Recalculation of void measurements

The present paper is a continuation of Part I: “Recalculation of single-phase and two-phase pressure loss measurements”. It deals with recalculations of void distribution measurements with the advanced two-phase, three-field sub-channel code F-COBRA-TF. Again, experimental data of both the OECD/NRC BFBT benchmark and in-house tests in AREVA NP's KATHY loop are used.The results of the recalculations of the measurements especially demonstrate the capability of a three-field code to predict void fractions with good accuracy, whereas the code is not based on a conventional void correlation which derives void fraction from quality according to an empirical function. In fact, the code relies on interfacial friction correlations for each flow regime. The quantities volume fraction of continuous liquid, volume fraction of entrained liquid and volume fraction of vapor are variables in the basic transport equations, which it is directly solved for. Thereby, the F-COBRA-TF standard models - which are usually applied for all sorts of calculations (pressure loss, void distribution, lateral mixing, critical heat flux, etc.) - were used. As already in Part I of the present paper, it was not necessary to do special code tuning with respect to certain experiments.     

Void fraction estimation within rod bundles based on three-fluid model and comparison with x-ray CT void data

An interfacial shear stress equation in the dispersed-annular two-phase flow regime has been developed, which is based on a three-fluid model consisting of a liquid film on a rod, vapor and entrained liquid associated with a vapor flow. It is an extension of J.G.M. Andersen's procedure that provides a two-fluid interfacial shear stress equation using the drift flux parameters C₀ and V_gj. This interfacial shear stress equation can take into account a phase and velocity distribution through an equivalence between the drift flux parameters and the interfacial shear stress.

Using the three-fluid subchannel analysis code TEMPO with the three-fluid interfacial shear stress model, the capability of a three-fluid calculation using the drift flux parameters C₀ and V_gj that reproduce a measured void fraction is demonstrated. A comparison was made with advanced X-ray computed tomography (CT) void fraction data within a 4×4 rod bundle in diabatic 1 MPa pressure conditions. The three-fluid velocity field was estimated to be in good agreement with the experimental result of a void fraction.     

Effects of Mass Transfer Resistances in Fluid and Permeable Walls on Hydrogen Permeation in Tube-Type Metal Window

The gas lift pump concept based on the bubbling of an inert gas into the primary reactor coolant to enhance natural circulation is currently considered in a number of PbBi-cooled reactor concepts. Thus, the analysis of available void fraction data and the development of two-phase heavy liquid metal/gas flow calculational models have become an important issue in the study of advanced nuclear reactor systems. In the absence of the detailed two-phase flow information needed to develop a flow regime map and the associated interfacial relations, drift-flux models have often been used in the thermal-hydraulic analysis of nuclear and other systems. Accordingly, we consider, in the current paper, the analysis of five sets of experimental data with different geometries, working fluids, flow rates and void fraction ranges, with a view to obtaining a best fit to the data in the form of a drift-flux model. The results of the analysis show that, for systems with flowing fluid, it is possible to represent the heavy liquid metal void fraction data in the form of a drift-flux correlation with a residual error of as low as 0.016, thus offering an improvement over existing void correlations.     

Evaluation Model of Turbine Meter for Two-Phase Flow

An evaluation model of a turbine meter has been developed to predict two-phase liquid velocity. The model considers the effects of blade configuration and void fraction distribution. In order to verify its applicability, experiments in single-phase and two-phase flows were performed and the model was compared with existing theories. This report describes the model and the experimental results on single-phase and two-phase flows.