Improvement of the uncertainty method with model treatment and optimized global sensitivity analysis and its application to pressurized water reactor

被引：10

作者：

Xiong, Qingwen ^{[1
]}

Gou, Junli ^{[1
]}

Shan, Jianqiang ^{[1
]}

Hui, Yongbo ^{[2
]}

机构：

[1] Xi An Jiao Tong Univ, Sch Nucl Sci & Technol, State Key Lab Multiphase Flow Power Engn, Xian 710049, Peoples R China

[2] Nucl Power Inst China, Chengdu 610041, Peoples R China

来源：

ANNALS OF NUCLEAR ENERGY | 2020年 / 149卷

关键词：

Uncertainty method; BEPU; Uncertainty quantification; Sensitivity analysis; LBLOCA; QUANTIFICATION;

D O I：

10.1016/j.anucene.2020.107794

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：

Best estimate plus uncertainty methodology is an advanced technology for licensing application of the nuclear power plants, but some aspects can still be improved in the conventional input-driven methodologies. For instance, uncertainties of the closure models are not properly handled; local sensitivity analysis methods not suitable for complex nuclear systems are still widely utilized; the sensitivity analysis process needs to be performed again every time new parameters are identified. Optimization researches were carried out in the study. A structural method was proposed to quantify the uncertainties of the closure models, and a low-cost moment-independent global sensitivity analysis method was developed to improve the sensitivity analysis framework. By integrating the improvements into the conventional input-driven framework, an uncertainty method with model treatment and improved sensitivity analysis was obtained. Finally, the method was validated through a large break loss of coolant accident in a three-loop pressurized water reactor. (C) 2020 Elsevier Ltd. All rights reserved.

引用

页数：13

共 35 条

[11]

Ishii M., 1981, CORRELATION LIQUID E, P81

[12] Investigation of uncertainty quantification method for BE models using MCMC approach and application to assessment with FEBA data [J].

Li, Dong ;

Liu, Xiaojing ;

Yang, Yanhua .

ANNALS OF NUCLEAR ENERGY, 2017, 107 :62-70

[13] AREVA's realistic large break LOCA analysis methodology [J].

Martin, RP ;

O'Dell, LD .

NUCLEAR ENGINEERING AND DESIGN, 2005, 235 (16) :1713-1725

[14]

Nissley M., 2003, Westinghouse Propriety Report, WCAP-1

[15] Quantifying Multiple Types of Uncertainty in Physics-Based Simulation Using Bayesian Model Averaging [J].

Park, Inseok ;

Grandhi, Ramana V. .

AIAA JOURNAL, 2011, 49 (05) :1038-1045

[16]

PAWEL RE, 1977, ORNLNUREG31

[17] Uncertainty and sensitivity analysis of a LBLOCA in a PWR Nuclear Power Plant: Results of the Phase V of the BEMUSE programme [J].

Perez, M. ;

Reventos, F. ;

Batet, L. ;

Guba, A. ;

Toth, I. ;

Mieusset, T. ;

Bazin, P. ;

de Crecy, A. ;

Borisov, S. ;

Skorek, T. ;

Glaeser, H. ;

Joucla, J. ;

Probst, P. ;

Ui, A. ;

Chung, B. D. ;

Oh, D. Y. ;

Pernica, R. ;

Kyncl, M. ;

Macek, J. ;

Manera, A. ;

Freixa, J. ;

Petruzzi, A. ;

D'Auria, F. ;

Del Nevo, A. .

NUCLEAR ENGINEERING AND DESIGN, 2011, 241 (10) :4206-4222

[18] INTEGRATED METHODOLOGY FOR THERMAL-HYDRAULIC CODE UNCERTAINTY ANALYSIS WITH APPLICATION [J].

Pourgol-Mohamad, Mohammad ;

Modarres, Mohammad ;

Mosleh, Ali .

NUCLEAR TECHNOLOGY, 2009, 165 (03) :333-359

[19]

Reventos F., 2016, PREMIUM BENCHMARK QU, P1

[20]

Reventos F., 2009, BEMUSE PHASE 5 REPOR

← 1 2 3 4 →