首页|SGTR事故工况下射流行为模拟实验研究

SGTR事故工况下射流行为模拟实验研究

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蒸汽发生器传热管破口(SGTR)事故属于铅冷快堆(LFR)中一类较为严重的事故。在SGTR事故工况下,二回路冷却剂水会与一回路中的高温熔融铅铋合金直接接触,从而发生强烈的相互作用。为了进一步研究水射流在熔融铅铋中的注入行为,本研究设计和搭建了液体射流两相流动可视化实验平台,并进行了一系列模拟实验。研究中首先探讨了沸腾(包含闪蒸)和非沸腾工况下的射流流型演化过程及规律,并定量分析了射流注入速率对最大注入深度的影响规律,最后基于实验数据运用Froude数理论对非沸腾工况下注入速度与最大注入深度进行了分析,并获得了无量纲半经验关系式。
Study of Jet Behavior Under SGTR Accident Conditions With Simulant Experiment
Steam Generator Tube Rupture(SGTR)accident is one of the severe events in the Lead-cooled Fast Reactor(LFR).Under SGTR accident conditions,the secondary loop coolant water comes into direct contact with the high temperature molten Lead-Bismuth Eutectic alloy(LBE)in the primary loop,resulting in a vigorous interaction.To further investigate the injection behavior of water jets in molten LBE,an experimental platform for visualizing the two-phase flow of liquid jets was designed and constructed in this study,and a series of simulant experiments were carried out.In this study,the evolution of jet flow patterns in boiling(including flashing jets)and non-boiling conditions was first investigated.The effect of injection rate on the maximum injection depth was also quantitatively analyzed.At last,based on the experimental data,the Froude number theory was applied to analyze the injection velocity and the maximum injection depth under non-boiling conditions,and a dimensionless semi-empirical relationship was obtained.

lead-cooled fast reactorsteam generator tube rupture accidentsjet injection depthjet behavior

陈松徽、程辉、成松柏

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中山大学中法核工程与技术学院,珠海 519082

哈尔滨工程大学核科学与技术学院,哈尔滨 150001

铅冷快堆 蒸汽发生器破口事故 射流注入深度 射流行为

广东省科技计划项目广东省自然科学基金广东省自然科学基金

2021A05050300262021A15150103432022A1515011582

2024

工程热物理学报
中国工程热物理学会 中国科学院工程热物理研究所

工程热物理学报

CSTPCD北大核心
影响因子:0.4
ISSN:0253-231X
年,卷(期):2024.45(4)
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