CAJ | 학술논문

核电站蒸汽发生器二次侧为两相对流沸腾换热过程，在设计过程中须保证其不发生两相流不稳定性。本工作采用时域法对垂直上升管内两相流不稳定性进行研究，建立了垂直上升直管内流动沸腾过程的一维模型，并编制计算程序。采用该程序模拟了流动沸腾过程气液两相流密度波的不稳定性，给出两相流波动过程瞬态参数分布，由此分析了密度波不稳定发生的机理，并分析了质量流速、系统压力、入口过冷度对不稳定的影响。结果表明，与已有实验及理论结果相比，瞬态参数计算结果与实验结果符合较好，可较好找到不同工况下直管内气液两相流发生不稳定的边界，结果优于K habenski线算图方法。
핵전참증기발생기이차측위량상대류비등환열과정，재설계과정중수보증기불발생량상류불은정성。본공작채용시역법대수직상승관내량상류불은정성진행연구，건립료수직상승직관내류동비등과정적일유모형，병편제계산정서。채용해정서모의료류동비등과정기액량상류밀도파적불은정성，급출량상류파동과정순태삼수분포，유차분석료밀도파불은정발생적궤리，병분석료질량류속、계통압력、입구과랭도대불은정적영향。결과표명，여이유실험급이론결과상비，순태삼수계산결과여실험결과부합교호，가교호조도불동공황하직관내기액량상류발생불은정적변계，결과우우K habenski선산도방법。
The secondary side of the nuclear power plant steam generator is working in a two-phase convective boiling process in which two-phase flow instability must be avoided in design . The time domain method was used to study the two-phase flow instability in a vertical up-flow tube . One-dimensional model was established and a numerical program was compiled .Two-phase flow density-wave instability was simulated ,and transient parameter distribution in the tube during the dynamic process was presented . The program was also used to analyze the effects of mass velocity ,system pressure ,and inlet sub-cooling on flow instability . T he result show s that the transient parameter distribution from the program agree well with the experimental results ,and it can predict the instability boundary ,w hich is more accurate than that of the usually used Khabenski nomographic method .