采用BETHSY自然循环实验数据对CATHARE2 V1.5qR6程序的评价

采用BETHSY自然循环实验数据对CATHARE2 V1.5qR6进行了评价.结果表明CATHRE2V1.5程序能较好地预测试验装置单相自然循环条件下的热工水力现象,对单相自然循环向两相自然循环的转变以及两相自然循环向回流冷凝运行方式的转变发生时的一回路水装量预测也比较准确,但对于两相自然循环及回流冷凝运行方式下系统的一些主要热工水力参数预测欠佳.评价结果表明,与许多国际性大型热工水力分析程序一样,CATHARE2V1.5qR6程序对剧烈两相流动的预测能力仍有待改进和完善.     

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。     

模块化压水堆非能动余热排出系统运行特性分析研究

针对初步设计的非能动余热排出系统方案并结合模块化反应堆的结构和运行特点,对非能动余热排出系统进行合理的控制体和节点划分并建立数学物理模型,采用数值迭代方法和通用热工水力分析程序,分析非能动余热排出系统的瞬态热工水力特性。结果表明,反应堆发生断电事故后,系统自然循环可以很快建立;在非能动余热排出过程中,换热器中二次侧始终为液相,没有发生流动不稳定;应急冷却器换热面积在一定范围内变化对系统余热排出能力没有显著影响。     

模块化压水堆非能动余热排出系统运行特性分析研究

针对初步设计的非能动余热排出系统方案并结合模块化反应堆的结构和运行特点,对非能动余热排出系统进行合理的控制体和节点划分并建立数学物理模型,采用数值迭代方法和通用热工水力分析程序,分析非能动余热排出系统的瞬态热工水力特性。结果表明,反应堆发生断电事故后,系统自然循环可以很快建立;在非能动余热排出过程中,换热器中二次侧始终为液相,没有发生流动不稳定;应急冷却器换热面积在一定范围内变化对系统余热排出能力没有显著影响。     

AP1000冷却剂强迫流动全部丧失事故瞬态特性分析

AP1000反应堆是目前国际上典型的"三代"核电厂,利用RELAP5/MOD 3.3程序对AP1000核电厂一回路系统进行整体建模,分析冷却剂强迫流动全部丧失事故下一回路主要热工水力参数的瞬态特性,并与COAST和LOFTRAN程序的计算结果进行了对比,发现两者具有相同的分布规律,表明利用RELAP5程序建立的计算模型可以准确模拟AP1000冷却剂强迫流动全部丧失事故下的热工水力特性。     

一维自然循环比例分析的结果与讨论

根据一维自然循环比例分析理论模型推导的试验装置与实际电站热工水力特性的相似准则,对整体性能试验装置主要参数的确定方法进行了深入讨论。结果表明:采用小尺度、等压力、同工质的实验装置模拟实际系统自然循环现象更为准确实际,单相和两相自然循环比例准则可同时满足,不存在复杂比例变化带来的失真,不利因素是试验成本偏高。同工质非等物性(不等压)模拟能够降低试验成本,但比例参数不能满足从单相自然循环到两相自然循环的平滑过渡。如保持功率连续,其速度比和特征时间比会有所差异。     

多重耦合自然循环载热系统瞬态特性及其热工水力解耦

多重耦合自然循环载热系统热工水力具有流动换热耦合和回路间耦合的特点,本文采用理论分析结合数值计算的方法对自然循环的建立时间、流动方向及多重耦合自然循环系统的热工水力解耦等问题进行了研究。提出了自然循环载热系统瞬态流动的理论模型,该模型能预测自然循环建立时间、流动衰减等现象,模型计算结果与数值计算结果吻合。初始流速为零的自然循环流动方向与系统的加热及冷却设备布置位置有关,垂直布置换热面使系统具有固有循环流动方向。具有初始流速的自然循环系统,即使换热面垂直布置,初始反向流速超过临界流速后也可使自然循环系统流动方向发生翻转,从而使系统在与固有循环流动方向相反的方向运行。提出了多重耦合自然循环载热系统热工水力的简单解耦计算方法,能快速对多重耦合自然循环载热系统热工水力进行分析计算,理论分析和计算结果均表明,以水为工质的自然循环回路载热能力近似与冷热源温差的1.5次方呈正比。     

秦山300MW核电机组全范围仿真机RCS及SG的建模与仿真

本文介绍了一个用于ＰＷＲ一回路实时仿真及分析的两相热工水力模型。模型以五个基本守恒方程为基础，考虑了非均相，不平衡态的效应。该模型已成功地用于秦山３００ＭＷ核电机组全范围仿真机主冷却剂系统及Ｕ型管蒸汽发生器的仿真。验收测试证明，模型能够准确有效地仿真核汽供给系统的热工水力特性。     

200 MW低温核供热堆非能动余热排出系统动态分析

200 MW低温核供热堆的余热排出系统由3个耦合的自然循环回路组成.本文对该系统的热工水力特性进行了理论分析.在一维质量、动量和能量守恒方程的基础上建立了非能动余热排出系统的数学模型,并编制程序对模型进行了数值求解,模拟了非能动余热排出系统的瞬态特性.经验证,该系统的排热能力满足设计要求.     

大型先进压水堆非能动冷却水箱关键热工水力特性研究综述

第3代大型先进压水堆设置非能动余热排出系统,包括大容积高位水箱及其内置的非能动余热排出热交换器(PRHR HX)和自动降压系统(ADS)喷洒器,在运行过程中呈现出复杂的气液两相热工水力现象和独特的传热、传质特性。近年来随着非能动安全系统工程需求和相关研究的兴起,国内外开展了一些针对大容积非能动冷却水箱及其内置关键部件热工水力特性的相关研究,本文对上述问题的研究现状进行综述。对于PRHR HX,评价特殊C型管束在单相自然对流、两相沸腾条件下的传热特性,分析经典传热模型及改进经验关联式的适用性;对于ADS 1～3级喷洒器高温高压蒸汽喷放冷凝过程,综合分析其喷放冷凝流型、特征参数、冷凝换热系数等关键传热、传质特性。以上研究大幅丰富了第3代大型先进压水堆大容积水箱的设计理论,并进行了实际工程应用。本文在此基础上,对相关研究未来发展方向进行展望。     

用集总参数法分析低含汽量自然循环回路汽液两相流稳定性

采用集总参数法分析低含汽量自然循环回路汽液两相流稳定性。描述热工水力现象的系统方程由均流模型偏微分守恒方程经集总参数平均导出，高含汽量常微分方程解程序包ＬＳＯＤＥ被用来解以常微分方程表征的系统方程，与清华大学核能技术研究院为分析５ＭＷ低温核供热堆热工水力特性而设计运行的两相流稳定性实验结果比较表明，采用集总参数法分析低含的自然循环回路两相流密度波振荡及其有关非线性现象是有效的。     

A new method to derive one set of scaling criteria for reactor natural circulation at single and two-phase conditions

Natural circulation is one of the most important thermal-hydraulic phenomena that makes the fluid flow along a closed loop without any external driving force. With this merit, it is adopted by the passive heat removal system to bring the residual heat out of the core at accidents, and by the primary system of some new conceptual reactors instead of pumps to drive the coolant in the loop at operation. To investigate the reactor natural circulation and verify system thermal-hydraulic codes, it is a way to construct an integrated effect test facility and perform experiments on it with the scaling criteria. With one-dimensional assumption, the natural circulation system was simplified as the heat source, heat sink and pipes, and described by two groups of equations independently for the single-phase and two-phase flow conditions. Based on these equations, a set of non-dimensional equations were derived and the criteria were obtained both applicable for single-phase and two-phase natural circulation. According to these criteria, the practical application was analyzed and discussed. In the paper, the property similarity was strongly suggested in most cases. Though equal height simulation was widely used in the past, the reduced height simulation is a good way to reproduce three-dimensional (3D) phenomena that are of concern in the investigation. The CHF simulation is not suggested. The mass of metal and its distribution is of concern instead of heat transfer at transient simulation.     

Experimental study on the natural circulation of a passive residual heat removal system for an integral reactor following a safety related event

Natural circulation characteristics of an integral type reactor during the operation of a passive residual heat removal system (PRHRS) following a safety related event has been experimentally investigated by using the VISTA facility. A PRHRS actuation trip signal is generated by a high power trip signal following a steam flow increasing event. The experimental results show that the single-phase coolant flows steadily in the primary loop by a natural convection process and that it effectively removes the decay heat from the core through a steam generator during the PRHRS operation. The heat transfers through the PRHRS heat exchanger and the emergency cooldown tank (ECT) are sufficient enough to enable a two-phase natural circulation of the coolant in the PRHRS loop.     

Scaling laws for thermal-hydraulic system under single phase and two-phase natural circulation

Scaling criteria for a natural circulation loop under single phase and two-phase flow conditions have been derived. For a single phase case the continuity, integral momentum, and energy equations in one-dimensional area average forms have been used. From this, the geometrical similarity groups, friction number, Richardson number, characteristic time constant ratio, Biot number, and heat source number are obtained. The Biot number involves the heat transfer coefficient which may cause some difficulties in simulating the turbulent flow regime. For a two-phase flow case, the similarity groups obtained from a perturbation analysis based on the one-dimensional drift-flux model have been used. The physical significance of the phase change number, subcooling number, drift-flux number, friction number are discussed and conditions imposed by these groups are evaluated. In the two-phase flow case, the critical heat flux is one of the most important transients which should be simulated in a scale model. The above results are applied to the LOFT facility in case of a natural circulation simulation. Some preliminary conclusions on the feasibility of the facility have been obtained.     

Author index to volume 79

Scaling criteria for a natural circulation loop under single phase and two-phase flow conditions have been derived. For a single phase case the continuity, integral momentum, and energy equations in one-dimensional area average forms have been used. From this, the geometrical similarity groups, friction number, Richardson number, characteristic time constant ratio, Biot number, and heat source number are obtained. The Biot number involves the heat transfer coefficient which may cause some difficulties in simulating the turbulent flow regime. For a two-phase flow case, the similarity groups obtained from a perturbation analysis based on the one-dimensional drift-flux model have been used. The physical significance of the phase change number, subcooling number, drift-flux number, friction number are discussed and conditions imposed by these groups are evaluated. In the two-phase flow case, the critical heat flux is one of the most important transients which should be simulated in a scale model. The above results are applied to the LOFT facility in case of a natural circulation simulation. Some preliminary conclusions on the feasibility of the facility have been obtained.     

Natural circulation experiments with a VVER reactor geometry

Experiments were conducted to study natural circulation behaviour in the PACTEL facility, a medium-scale integral test loop patterned after Soviet-designed VVER pressurized water reactors. Using stepwise inventory reduction and small-break experiments, primary loop flow behaviour was studied over a range of coolant inventories. The tests revealed a trend toward decreasing primary side mass flow rate with inventory. In the small-break experiments, flow stagnation and system repressurization were observed when the water level in the upper plenum fell below the entrances to the hot legs and coolant flow into the hot legs changed from single to two-phase flow. The cause of this flow interruption was attributed to the hot leg loop seals, which are a unique feature of the VVER geometry. Finally, an experiment was conducted to demonstrate how loop seal refilling behaviour at low coolant inventories depends upon the steam flow rate through an individual hot leg. It was shown that loop seal refilling results when low steam velocities permit countercurrent flow in the upflow side of the loop seal.     

非能动安全壳冷却系统空气流道自然循环的比例分析与设计

在考虑建设试验台架经济性的前提下,缩小比例的单项和整体效应试验台架对研究和开发大型先进压水堆核电站及其分析验证程序都具有重要意义。非能动安全壳冷却系统（PCS）壳外空气流道内的自然循环在安全壳非能动冷却性能中发挥着重要的作用。本文从自然循环的数学模型出发,推导出了单项和整体效应试验台架的比例设计方法。在给定壳内热流密度的条件下,通过PCCSAP-3D程序对CAP1400非能动安全壳的2/5比例单项效应试验理想比例台架（ISF）进行模拟。结果表明,本比例分析与设计方法以及在降低高度台架上模拟自然循环是可行的。     

低压低功率条件下两相自然循环特性试验研究

相比于陆基核电厂,船用核动力装置的非能动安全系统运行压力较低,运行功率变化频繁,在两相自然循环条件下,非能动安全系统内的流动更加复杂多变。为了研究两相自然循环在低压、低功率条件下的循环特性,基于比例分析方法搭建了两相自然循环的原理试验台架,研究了低压条件下功率和初始液位高度对自然循环特性的影响。结果表明,在低压条件下,系统稳定运行后的压力、流量等均受初始液位高度和功率的影响。当功率为50 kW时,初始液位越高,系统稳定后的压力越大,但是流量相差较小;初始液位一定时,功率在40%满功率~100%满功率内,随着功率的增大,系统稳定后的压力也逐渐增大。这为试验台架后续两相自然循环的研究提供了方向,也为船用核动力装置非能动安全系统研究提供了参考。      

二次侧非能动余热排出系统传热能力试验研究

通过搭建试验装置，针对二次侧非能动余热排出系统（ASP），开展了试验研究。本文对ASP整体性能响应和稳态特性试验研究的试验装置、试验工况、试验结果进行了介绍。试验结果表明，在模拟事故工况下，ASP可稳定建立自然循环，并将回路热量导出，保证系统整体安全性；稳态特性试验中，回路压力为8 MPa时，可导出设计热量，且随压力的升高，导热能力增大，水箱温度对于换热影响较小。