Stochastic finite elements analysis of large concrete structures' serviceability under thermo-hydro-mechanical loads - Case of nuclear containment buildings

被引:23
作者
Bouhjiti, D. E. -M. [1 ,2 ,3 ,7 ]
Baroth, J. [1 ,2 ]
Dufour, F. [1 ,2 ,4 ]
Michel-Ponnelle, S. [5 ]
Masson, B. [6 ]
机构
[1] Univ Grenoble Alpes, CNRS, Grenoble INP, 3SR, F-38000 Grenoble, France
[2] Univ Grenoble Alpes, Inst Engn, Grenoble, France
[3] Grenoble INP Partnership Fdn Ind Chair PERENITI, Grenoble, France
[4] PERENITI Chairholder EDF SEPTEN DTG CIH, Grenoble, France
[5] Elect France EDF R&D, Paris, France
[6] Elect France EDF DIPNN Tech Direct, Lyon, France
[7] Egis Ind, TSA 50012, F-93188 Montreuil, France
关键词
THM-L metamodeling; Stochastic Finite Element Methods; Uncertainty propagation; Local and global sensitivity analyses; Nuclear containment buildings; EARLY-AGE BEHAVIOR; POLYNOMIAL CHAOS; GAS-PERMEABILITY; LEAKAGE RATE; CREEP; DAMAGE; MODEL; HYDRATION; CRACKING; TEMPERATURE;
D O I
10.1016/j.nucengdes.2020.110800
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
This work proposes a global Stochastic Finite Element Method (SFEM) to model the effects of concrete ageing uncertainties on the serviceability and durability of large reinforced and prestressed structures with a containment role. As their modelling requires strongly non-linear, coupled and expensive calculations with a large number of parameters, adapted and efficient probabilistic strategies need to be defined aiming at a stochastic analysis within a reasonable cost and a physically admissible representativeness. In this contribution, this is achieved through four steps: (a) the definition of a well-established physical framework based on a staggered Thermo-Hydro-Mechanical + Leakage (THM-L) model; (b) the limitation of random inputs for uncertainty propagation to the most influential ones using a variance-based Hierarchized and Local Sensitivity Analysis (HLSA); (c) the construction of a THM-L response metamodel using Polynomial Chaos Expansion (PCE); (d) the reliability analysis of serviceability criteria using Crude Monte Carlo Method (CMCM) applied to the developed metamodel. For validation purposes and demonstration of achievability within a complex industrial framework, this global methodology is applied to an experimental 1:3 scaled Containment Building of a nuclear reactor. Eventually, it is shown that a complete probabilistic analysis of a physically admissible total dry air leakage rate (indicative of a nuclear containment structure's performance) and its evolution in time are obtained within a computational time of tens of days only. Such result can provide insights and help during the decision-making process for the design, maintenance and risk assessment of large structures. For Nuclear Containment Buildings (NCB), a direct application would be the evaluation of lifespan extension based on a leakage-rate-defined criterion under operational loads.
引用
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页数:27
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