摘要
为进一步探究核电厂安全壳内环境条件影响泄漏率测量的基本规律,自主研发了压降法安全壳泄漏率数据分析程序,并通过在大尺度安全壳模拟体上开展的泄漏率实验对测量结果进行验证。结合相应的实验数据研究了准稳态与非稳态环境条件下安全壳内温度和相对湿度变化对泄漏率测量值的影响。结果表明,在升温条件下,各温度传感器因所处热环境的差异而形成的不同升温速率会明显影响泄漏率的测量,测量值相比升温前的相对偏差可超过20%。此外,在壳内局部温湿度变化的非稳态环境下,压力与温度传感器的固有延迟效应还会导致泄漏率的测量出现异常。而当壳内温湿度维持恒定或各传感器的温湿度变化速率近似一致时,泄漏率测量值较稳定,可确定其为实际的泄漏率。该研究结论可为进一步认识安全壳泄漏率测量机理和方法优化提供参考。
In order to further explore the basic law that the environmental conditions in the nuclear power plant containment affect the leakage rate measurement,a data analysis program for measuring the containment leakage rate by the pressure drop method was developed in this investigation.The measurement results were validated by leakage rate measurement tests carried out on a large-scale containment simulant.Based on the test data,the effects of the temperature and relative humidity on the leakage rate measurements under quasi-steady-state and non-steady-state conditions were studied.The results show that in the heating environment,the different heating rates of each temperature sensor due to the difference in the thermal environment can significantly affect the measurement of the leakage rate,and the relative deviation of the measured value compared with the temperature before heating can exceed 20%.Moreover,in the unsteady environment of local temperature and humidity changes in the vessel,the inherent delay effect of the pressure and temperature sensors can also cause abnormal leakage rate measurements.However,when the temperature and humidity in the casing are kept constant or the temperature and humidity change rates of each sensor are approximately the same,the measured value of the leak rate is relatively stable.The conclusions provide a reference for further understanding the leakage rate measurement mechanism and method optimization.
作者
李建发
刘丰
滑永振
孙中宁
孟兆明
Li Jianfa;Liu Feng;Hua Yongzhen;Sun Zhongning;Meng Zhaoming(China Nuclear Power Engineering Co.,Ltd.,Beijing,100840,China;College of Nuclear Science and Technology,Harbin Engineering University,Harbin,150001,China)
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2023年第3期196-201,共6页
Nuclear Power Engineering
基金
重点研发计划资助(2020YFB1901405)。
关键词
核电厂安全壳
泄漏率
密封性实验
温度
相对湿度
压降法
Nuclear power plant containment
Leakage rate
Tightness test
Temperature
Relative humidity
Pressure drop method