A review of the fundamentals and methods of accident analysis using the best estimate plus uncertainty approach in nuclear power plants

被引:0
作者
Khoshmaram, Mehdi [1 ]
Shirani, Amir Saeed [1 ]
Sadeghi, Khashayar [2 ]
Sedghkerdar, Abbas [3 ]
Ghazaie, Seyed Hadi [2 ]
Sokolova, Ekaterina [2 ]
机构
[1] Shahid Beheshti Univ, Fac Engn, POB 1983969411, Tehran, Iran
[2] Peter Great St Petersburg Polytech Univ, Dept Nucl & Heat Power Engn, St Petersburg 195251, Russia
[3] Shiraz Univ, Sch Mech Engn, Dept Nucl Engn, Shiraz, Iran
关键词
Thermal-hydraulics; Severe accident analysis; Uncertainty analysis; Best Estimate Plus Uncertainty; BEPU methods; REACTOR SAFETY MARGINS; CODE UNCERTAINTY; SENSITIVITY THEORY; CONFIDENCE-LIMITS; RELIABILITY; PRISM;
D O I
10.1016/j.nucengdes.2025.113868
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
In 1989, the United States Nuclear Regulatory Commission (USNRC) revised the licensing rules for nuclear power plants (NPPs), allowing the conservative approach to be replaced by the Best Estimate Plus Uncertainty (BEPU) methodology. This replacement had two consequences: First, it became possible to use Best Estimate codes such as RELAP5 in licensing and design processes (previously, conservative codes were used). Second, methods were developed to study and quantify the uncertainty of these codes' results and implement the BEPU approach according to the developer's goal. The primary goal of the BEPU approach is to organize safety and thermalhydraulics (TH) concerns for NPP licensing processes and frameworks. This approach is not uniform and various methods are used to implement it, but some concepts and basics are common. Some methods are pioneering and have initiatives within their structure, such as CSAU, GRS, and UMAE. Others improve the weaknesses of the pioneer methods (such as IMTHUA). This study aims to clarify the fundamentals, review the implementation methods, and assess the progress of studies based on the BEPU approach.
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页数:20
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