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Stochastic finite elements analysis of large concrete structures’ serviceability under thermo-hydro-mechanical loads – Case of nuclear containment buildings
Nuclear Engineering and Design ( IF 1.7 ) Pub Date : 2020-12-01 , DOI: 10.1016/j.nucengdes.2020.110800 D.E.-M. Bouhjiti , J. Baroth , F. Dufour , S. Michel-Ponnelle , B. Masson
Nuclear Engineering and Design ( IF 1.7 ) Pub Date : 2020-12-01 , DOI: 10.1016/j.nucengdes.2020.110800 D.E.-M. Bouhjiti , J. Baroth , F. Dufour , S. Michel-Ponnelle , B. Masson
Abstract 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.
中文翻译:
热-水-机械载荷作用下大型混凝土结构使用性能的随机有限元分析——以核安全壳建筑为例
摘要 这项工作提出了一种全局随机有限元方法 (SFEM),以模拟混凝土老化不确定性对具有遏制作用的大型钢筋和预应力结构的适用性和耐久性的影响。由于它们的建模需要具有大量参数的强非线性、耦合和昂贵的计算,因此需要定义适应和有效的概率策略,以在合理的成本和物理上可接受的代表性内进行随机分析。在这一贡献中,这是通过四个步骤实现的:(a) 基于交错的热-水-机械 + 泄漏 (THM-L) 模型定义完善的物理框架;(b) 使用基于方差的分层和局部敏感性分析 (HLSA) 将不确定性传播到最有影响力的随机输入的限制;(c) 使用多项式混沌展开 (PCE) 构建 THM-L 响应元模型;(d) 使用适用于开发的元模型的原始蒙特卡罗方法 (CMCM) 对适用性标准的可靠性分析。为了验证目的和在复杂的工业框架内展示可实现性,这种全球方法被应用于核反应堆的实验性 1:3 规模的安全壳建筑。最终,结果表明,仅在几十天的计算时间内就获得了对物理上允许的总干空气泄漏率(指示核安全壳结构的性能)及其随时间演变的完整概率分析。这样的结果可以为大型结构的设计、维护和风险评估的决策过程提供见解和帮助。对于核安全壳建筑 (NCB),直接应用将是基于运行负载下泄漏率定义的标准来评估寿命延长。
更新日期:2020-12-01
中文翻译:
热-水-机械载荷作用下大型混凝土结构使用性能的随机有限元分析——以核安全壳建筑为例
摘要 这项工作提出了一种全局随机有限元方法 (SFEM),以模拟混凝土老化不确定性对具有遏制作用的大型钢筋和预应力结构的适用性和耐久性的影响。由于它们的建模需要具有大量参数的强非线性、耦合和昂贵的计算,因此需要定义适应和有效的概率策略,以在合理的成本和物理上可接受的代表性内进行随机分析。在这一贡献中,这是通过四个步骤实现的:(a) 基于交错的热-水-机械 + 泄漏 (THM-L) 模型定义完善的物理框架;(b) 使用基于方差的分层和局部敏感性分析 (HLSA) 将不确定性传播到最有影响力的随机输入的限制;(c) 使用多项式混沌展开 (PCE) 构建 THM-L 响应元模型;(d) 使用适用于开发的元模型的原始蒙特卡罗方法 (CMCM) 对适用性标准的可靠性分析。为了验证目的和在复杂的工业框架内展示可实现性,这种全球方法被应用于核反应堆的实验性 1:3 规模的安全壳建筑。最终,结果表明,仅在几十天的计算时间内就获得了对物理上允许的总干空气泄漏率(指示核安全壳结构的性能)及其随时间演变的完整概率分析。这样的结果可以为大型结构的设计、维护和风险评估的决策过程提供见解和帮助。对于核安全壳建筑 (NCB),直接应用将是基于运行负载下泄漏率定义的标准来评估寿命延长。