摘要
国内外核电厂安全壳泄漏率测量普遍采用绝对压力衰减法(简称压降法),现行技术标准中该方法基于多项假设条件。为了探究假设条件对泄漏率测量的影响,本研究依托中核工程廊坊研发基地的安全壳综合性能实验平台,建成大空间安全壳泄漏率测量系统,通过数值模拟及试验验证相结合的方法,分析了温度、压力、容积等关键假设条件对安全壳泄漏率测量结果的影响。研究发现,温度变化对泄漏率测量产生了影响,壳体温度变化1℃/d,泄漏率偏差超过0.003%;壳内小开口密闭空间产生的泄漏率测量影响与开口孔径、空间容积相关。研究最终提出了温度变化及小开口空间等因素影响泄漏率的补偿计算模型,为工程实践中泄漏率测量的修正提供了理论依据与技术支撑。
The Absolute Pressure Decay Method(hereinafter referred to as the"Pressure Drop Method")has been widely adopted for measuring containment leakage rates in nuclear power plants both domestically and internationally.This method,as stipulated in current technical standards,is based on multiple assumed conditions related to the test environment.To investigate the impact of these assumptions on leakage rate analysis,a large-scale containment leakage rate measurement system was established based on the comprehensive containment performance experimental platform at the Langfang R&D Base of CNPE.The influence of key assumptions such as temperature,pressure and volume on the measurement results of leakage rate was analyzed by combining numerical simulation and experimental verification.It was found that temperature has a significant influence on leakage rate assessment;specifically,a variation in the containment shell temperature of 1°C per day can result in a leakage rate deviation exceeding 0.003%.The effect of small opening spaces inside the containment on leakage rate measurements was found to be related to both the aperture size and the internal volume of these spaces.Based on these findings,a compensation calculation model was proposed to address the influences of temperature variations and small opening spaces,providing a theoretical basis and technical support for the correction of leakage rate measurements in engineering practice.
作者
李建发
刘明媚
高力
Li Jianfa;Liu Mingmei;Gao Li(China Nuclear Power Engineering Co.,Ltd.,Beijing,100840,China;Joint Laboratory for Thermal and Hydraulic Engineering of Containment Vessels,Beijing,100840,China;R&D Center of China Nuclear Power Engineering Co.,Ltd.,Langfang,Hebei,065000,China;CNNC Engineering Technology Development Co.,Ltd.,Langfang,Hebei,065000,China)
出处
《核动力工程》
北大核心
2025年第S2期24-30,共7页
Nuclear Power Engineering
基金
中核工程自主科研项目(KY25028)。
关键词
安全壳泄漏率
压降法
假设条件
补偿模型
Containment leakage rate
Pressure drop method
Assumed conditions
Compensation model
