Coupling Design and Validation Analysis of an Integrated Framework of Uncertainty Quantification

被引:0
|
作者
Pang, Bo [1 ]
Su, Yuhang [2 ]
Wang, Jie [1 ]
Deng, Chengcheng [2 ]
Huang, Qingyu [1 ]
Zhang, Shuang [1 ]
Wu, Bin [1 ]
Lin, Yuanfeng [1 ]
机构
[1] Nucl Power Inst China, Sci & Technol Reactor Syst Design Technol Lab, Chengdu 610213, Peoples R China
[2] Huazhong Univ Sci & Technol, Sch Energy & Power Engn, Dept Nucl Engn & Technol, Wuhan 430074, Peoples R China
关键词
uncertainty quantification; interface coupling; integrated framework; code validation; SENSITIVITY-ANALYSIS; BREAK LOCA; CODE; APPLICABILITY; MODEL;
D O I
10.3390/en16114435
中图分类号
TE [石油、天然气工业]; TK [能源与动力工程];
学科分类号
0807 ; 0820 ;
摘要
The uncertainty quantification is an indispensable part for the validation of the nuclear safety best-estimate codes. However, the uncertainty quantification usually requires the combination of statistical analysis software and nuclear reactor professional codes, and it consumes huge computing resources. In this paper, a design method of coupling interface between DAKOTA Version 6.16 statistical software and nuclear reactor professional simulation codes is proposed, and the integrated computing workflow including interface pre-processing, code batching operations, and interface post-processing can be realized. On this basis, an integrated framework of uncertainty quantification is developed, which is characterized by visualization, convenience, and efficient computing. Meanwhile, a typical example of small-break LOCA analysis of the LOBI test facility was used to validate the reliability of the developed integrated framework of uncertainty quantification. This research work can provide valuable guidance for developing an autonomous uncertainty analysis platform in China.
引用
收藏
页数:14
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