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Optimization Model of Measurement Uncertainty of Leakage Rate of Nuclear Power Plant Containment
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Published:   2026-07-17
Publication Date:   2026-07-17
Online:   2026-07-17
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Abstract:

The NB/T 20018 standard does not provide a model for the Type B measurement uncertainty of the containment leakage rate. In order to perfect the theoretical model concerning the containment leakage rate within this standard and to further enhance its instructiveness in engineering experiments, a Type B uncertainty analysis model for the containment leakage rate has been proposed in this study. Firstly, based on the uncertainty theory in the JJF 1059 metrological standard, a theoretical model for Type B measurement uncertainty was developed for the containment leakage rate calculation formula specified in NB/T 20018. Subsequently, experiments were conducted with sensors deployed in a 1000m3 steel containment mock-up to validate the effectiveness of the model and to explore the factors influencing uncertainty. Furthermore, the uncertainty model proposed in this paper was utilized to analyze the pressure test data of the Hualong One containment, thereby verifying the accuracy of the theoretical model in engineering-scale tests. The research results indicate that the combined uncertainty calculated using the model proposed in this study is consistent with the combined uncertainty calculated using the standard method, with a relative deviation of only 6%. Type A uncertainty is found to be related to the gas state inside the containment and the duration of the test, while Type B uncertainty is associated with the uncertainty of the instruments and their quantity. The conclusions of this study can serve to provide theoretical support for the improvement of the NB/T 20018 standard and promote the independent development of containment sealing test technology.

References

[1]褚英杰,欧阳钦. 安全壳整体泄漏率计算方法的比较分析[J]. 核动力工程, 2010, 31(6):33-37

[2] 孙流莉,阳祥,赵瑞昌,等. 安全壳冷却试验蒸发特征数不确定度评定方法及其应用[J]. 动力工程学报, 2015, 35(8):688-691

[3] 詹淑文,常华健. 不确定度理论在核电站安全壳泄漏率计算中的应用[J]. 核动力工程, 2006,27(4):202-205

[4] 蒋坚毅,郭红晓,李安明,等. 核电厂安全壳泄漏率测定的不确定度评定[J]. 仪器仪表学报, 2006, 27(12):11-14

[5] 冯利法,黄海涛. 核电厂钢制安全壳泄漏率测试系统的开发与验证[J]. 核科学与工程, 2021, 41(6):1159-1161

[6] American Nuclear Society Standards Committee. Containment system leakage testing requirements. ANSI/ANS 56.8-2002[S]. U.S.: American Nuclear Society, 2002

[7] 法国电力部. RCC-G 88, 压水堆核岛土建设计与建造堆规程[S], 法国: 法国核岛设备设计与建造规程协会, 1988

[8] 能源行业核电标准化技术委员会. NB/T 20018-2021,压水堆核电厂安全壳密封性试验[S], 北京: 国家能源局, 2021

[9] 全国法制计量管理计量技术委员会. JJF 1059.1-2012 测量不确定度评定与表示[S]. 北京: 国家质量监督检验检疫总局, 2012

[10] 李建发,刘丰,滑永振,等. 压降法测量核电厂安全壳泄漏率的影响因素研究[J]. 核动力工程, 2023, 44(3):198-201

Basic Information:

China Classification Code:TM623

Citation Information:

[1]LIU Mingmei,LI Jianfa,HUA Yongzhen.Optimization Model of Measurement Uncertainty of Leakage Rate of Nuclear Power Plant Containment[J].Nuclear Science and Engineering().

Fund Information:

中核工程自主科研项目(KY22236安全壳密封性试验技术研究)

Published:  

2026-07-17

Publication Date:  

2026-07-17

Online:  

2026-07-17

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