SGTR事故工况下射流行为模拟实验研究
Study of Jet Behavior Under SGTR Accident Conditions With Simulant Experiment
陈松徽 1程辉 2成松柏1
作者信息
- 1. 中山大学中法核工程与技术学院,珠海 519082
- 2. 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
- 折叠
摘要
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.
Abstract
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.
关键词
铅冷快堆/蒸汽发生器破口事故/射流注入深度/射流行为Key words
lead-cooled fast reactor/steam generator tube rupture accidents/jet injection depth/jet behavior引用本文复制引用
基金项目
广东省科技计划项目(2021A0505030026)
广东省自然科学基金(2021A1515010343)
广东省自然科学基金(2022A1515011582)
出版年
2024
NETL
NSTL
维普
万方数据