基于CATHARE程序的自然循环静态流量漂移模拟

针对中低压自然循环系统静态流量漂移现象的特点,利用大型系统热工程序CATHARE对不同压力和阻力分布下的自然循环系统进行模拟分析,探索静态流量漂移的影响因素。分析结果表明,同等过冷度条件下,低压更易诱发静态流量漂移;加热段出口阻力分布对阻力影响较大。同时,结合计算数据分析系统静态分岔及迟缓现象。     

强迫循环并联通道流量漂移现象研究

使用RELAP5程序对垂直并联环隙窄缝通道流量漂移现象进行研究,分析了强迫循环并联通道流量漂移现象的形成过程及其原因,研究了主要运行参数对垂直并联环隙窄缝通道流量漂移现象的影响。结果表明:增大窄缝间隙,降低入口欠热度,增大系统压力,减小热流密度,增加入口单相阻力,减小出口两相阻力均可减小通道压降-流量特性曲线的斜率,从而提高系统的稳定性,避免流量漂移现象的发生。     

自然循环静态流动不稳定研究

研究了发生静态流量漂移时自然循环系统中流量和加热段进出口温度的变化规律及静态流漂移过程中发生的动态流量振荡现象。研究结果表明：在发生静肪流量漂移时，系统循环流量下降，、加热段的进口温度下降而出口温度上升；当静态流量漂移一段时间后，伴随着静态流量漂移，系统内同时发生动态流量振荡。在对现象描述的基础上，阐述了静态流量漂移发生的机理。     

低压低干度自然循环流量漂移分析

在 5MW核供热堆全尺寸全参数模拟试验回路HRTL 5上进行的实验中 ,观察到在一定条件下系统发生静态流量漂移的同时 ,伴随动态流量振荡。本文总结了HRTL 5模拟试验回路上的实验研究结果 ,分析了低压低干度自然循环系统的特点、欠热沸腾和闪蒸的作用机理 ,较完整地描述了自然循环流量漂移的整个过程。分析结果表明 :1 )在自然循环系统中 ,欠热沸腾和闪蒸对流动稳定性具有重要作用 ;2 )自然循环流量漂移是一个长热工过程 ,动态振荡也可以发生在静态流量漂移过程中 ;3 )在静态流量漂移的发生、发展并向动态振荡转变的过程中 ,先是欠热沸腾占主导地位 ,然后逐渐转变为闪蒸占主导地位 ,最后主要表现为密度波振荡的形式。自然循环流量漂移对 5MW堆的设计、安全分析以及升级开发具有重要价值。     

低干度自然循环流量漂移的特征曲线图谱分析

在5MW低温核供热堆全模拟试验回路(HRTL-5)上,实验观察到了低干度自然循环条件下的流量漂移现象.通过一个考虑了加热段欠热沸腾、上升段冷凝、闪蒸等物理过程的两相流动数学模型,编制了相应的计算程序,获得了自然循环特征曲线图谱及其运行曲线,确定了自然循环分岔图和静态不稳定边界图,进而提出了通过自然循环特征曲线图谱研究流量漂移的分析方法.分析表明:特征曲线图谱方法是研究自然循环静态不稳定的有效手段.增大系统压力、减小热流密度、增加入口单相阻力、减小出口两相阻力有利于避免自然循环流量漂移的发生.     

200MW低温堆主换热嚣阻力特性实验研究

通过1:2.33的实验模型,对大庆200MW低温核供热堆主换热器进行了水力学模拟研究。研究结果表明:当Re>5000时,换热器的阻力系数已进入自模区。给出了换热器达到自模时的阻力系数及各流程间的流动阻力分布。提出了减少出口段流动阻力的优化设计方案。阻力系数的设计值与模拟研究结果相吻合。描述了发生两次流量漂移现象时,各系     

平行通道流动不稳定性研究

并联通道的不稳定性是两相流学科中的重要研究方向。本文针对强迫循环并联环隙窄缝通道系统,使用RELAP5/MOD3.4程序进行分析,研究了平行通道系统的流动不稳定特性。指出在加热通道的水力直径较小时,平行通道系统中存在管间脉动和管间流量漂移两种不稳定现象。根据水动力特性曲线的特性,分析了这两种不稳定现象的形成及发展过程,得出主要运行参数对平行通道管间流量漂移不稳定性的影响规律。     

自然循环流量漂移伴随动态振荡的机理分析

在 5MW核供热堆试验回路HRTL 5上观察到了一定条件下系统发生的静态流量漂移并同时伴随动态流量振荡的现象。本文在实验基础上 ,研究了流量漂移的发生、发展和向动态振荡演变的过程 ,以及欠热沸腾、冷凝、闪蒸在此过程中的作用机理。分析结果表明 :1 )自然循环流量漂移是一个长热工过程 ,动态振荡可发生在静态漂移过程中 ;2 )在流量漂移的过程中 ,先是欠热沸腾和冷凝占主导地位 ,然后渐变为闪蒸占主导地位 ,最终表现为自持振荡形式 ;3)最终的自持振荡主要表现为密度波振荡 ,又具备喷泉不稳定的特征。     

窄矩形通道内低压两相自然循环流量漂移实验研究

在自然循环实验台架上进行窄矩形通道自然循环流量漂移实验研究。当加热到一定功率时,系统开始出现自然循环流量漂移,且流量漂移过程中伴随着流量振荡;整个系统的稳定性随着入口流体欠热度、压力、缝隙宽度的增加而增大。通过欠热度数、相变数等参数绘制出系统的稳定性曲线。发现窄矩形通道流量漂移存在4阶段机理,并提出窄矩形自然循环流量漂移起始功率经验关系式。     

HRTL-5自然循环稳态特性

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低温核供热堆热工水力模拟回路（HRTL-5）的自然循环稳态特性进行模拟,分析了HRTL-5自然循环流量特性及其参数效应。结果表明：1)漂移流模型比均相流模型更适用于HRTL-5;2)当系统压力为1.5MPa时,系统自然循环流量随加热热流密度的升高而增加;3)当系统压力为0.5MPa时,系统自然循环流量随加热热流密度的升高先增加后减小;4)自然循环流量随加热段入口欠热度的升高而减小;5)当加热热流密度较低时,〖JP3〗系统自然循环流量随压力的升高而减小,当加热热流密度较高时,系统自然循环流量随压力的变化呈现复杂状况。     

Flow excursion phenomenon and its mechanism in natural circulation

An experiment was performed on the test loop (HRTL-5), which simulates the geometry and system design of a 5-MW nuclear heating reactor. In a wide range of inlet subcoolings, different flow modes, such as single-phase stable flow, subcooled boiling stable flow, subcooled boiling static flow excursion, density-wave oscillation and stable two-phase flow in the natural circulation system have been described. The phenomenon and mechanism of the static flow-excursion, which has never been studied well on this field, is especially interpreted. The experimental results show that, in the process of flow excursion, the mass flow rate and the inlet temperature decreases, while the exit temperature increases smoothly. As the process of the excursion continues for about 1 h, short period dynamic flow oscillation occurs, which can only be seen in the process of this static flow excursion, and has also never been studied well. These static and dynamic flow instabilities combine together and continue for about 2 h, then a point is reached, at which the static flow excursion disappears, but the dynamic flow oscillation continues. The mechanism of the static flow excursion is interpreted through two sets of curves for flow resistance pressure drop and driven head in natural circulation, and one curve for the natural circulation operation under special thermohydraulic condition. The study of the flow excursion and its concerned dynamic flow oscillation is of great significance for the development of the nuclear heating reactor under natural circulation.     

RELAP5/3.2 assessment against low pressure onset of flow instability in parallel heated channels

Best Estimate computer codes have been, so far, developed for safety analysis of nuclear power plants and were extensively validated against a large set of separate effects and integral test facilities experimental data relevant to such kind of reactors. Their application to research reactors is not fully straightforward. Modelling problems generally emerge when applying existing models to low pressure and more particularly to subcooled flow boiling situations. The objective of the present work is to investigate the RELAP5/3.2 system code capabilities in predicting phenomena that could be encountered under abnormal research reactor’s operating conditions. For this purpose, the separate effect related to the static onset of flow instability is investigated. The cases considered herein are the flow excursion tests performed at the Oak Ridge National Laboratory thermal hydraulic test loop (THTL) as well as some representative Whittle and Forgan (W & F) experiments. The simulation results are presented and the capabilities of RELAP5/Mod 3.2 in predicting this critical phenomenon are discussed.     

Assessment of Some Cross Section Libraries through Analyses of Coupled-Core Critical Experiments by Monte Carlo Calculations

An experiment was performed on the natural circulation test loop HRTL-5, which simulates the geometry and system design of the 5 MW full power natural circulation nuclear heating reactor. Different flow modes, including density wave oscillation and flow excursion et al., were observed in a wide range of inlet sub-cooling at 1.5MPa. By means of self-developed computational codes, the bifurcation chart has been obtained. Consequently the flow excursion boundary has been determined. Through the analysis on the excursion boundary, the method to avoid the flow excursion during startup has been presented. Analytical results show: (1) with the decreasing heat flux or the increasing system pressure, the static flow excursion occurs at higher inlet temperature and its range in the instability maps becomes narrower correspondingly; (2) to decrease the outlet two-phase resistance or increase the inlet single-phase resistance is beneficial to avoid the flow excursion; (3) by means of increasing the system pressure to start up the reactor with low heat flux, the flow excursion and low steam quality density wave oscillation can be successfully avoided. This investigation is meaningful to the reactor safety and the design of the nuclear heating reactors.     

矩形窄缝自然循环密度波不稳定特性实验研究

以去离子水为工质,对其两相自然循环流动不稳定性进行了实验研究,得到了2mm和5mm的矩形缝隙条件下的流量变化情况。实验结果分析表明:2mm矩形窄缝的流量波动周期为4~5s,5mm的流量波动周期为5~7s;2mm矩形窄缝的上下振幅对称性不佳,5mm的上下振幅对称性较好;随着加热量的增加,2mm和5mm矩形窄缝的波动周期均会增大。2mm矩形窄缝随着功率的增加,出现了流量漂移,密度波波动特征减弱。