首页> 外文期刊>Annals of nuclear energy >Fragility analysis of prestressed concrete containment under severe accident condition
【24h】

Fragility analysis of prestressed concrete containment under severe accident condition

机译:严重事故条件下预应力混凝土安全壳的脆性分析

获取原文
获取原文并翻译 | 示例
           

摘要

Nuclear containment structure is the most important shielding structure in nuclear power plant, the main function of the containment structure is to prevent the leakage of radioactive materials into environment during the accident conditions, it is of great significance to gain insight into the performance of the containment under severe accidents. This paper presents fragility analysis of prestressed concrete containment vessels under severe accidents. Firstly, detailed three-dimensional finite element model of the containment is established, material nonlinearity and non-uniform effective prestressing distribution along the prestressed tendons is also considered. Secondly, Latin hypercube sampling technique combined with MATLAB program and python script is developed to update the material parameters in ABAQUS input files to generate 30 random samples. Fragility curves of five critical locations with consideration of aleatory uncertainty and epistemic uncertainty and fragility curves with different confidence levels had been thoroughly investigated. Finally, sensitivity analysis for input random variables had been conducted to provide better understanding of the significance of the various random parameters. Results indicate that functional failure of containment is dominated by the location of equipment hatch. The difference between the HCLPF pressure capacity obtained from the composite fragility curve and the lower bound pressure capacity of the containment obtained from fragility curve with 95% confidence is small. The lower bound pressure capacity and upper bound pressure capacity is 0.837 MPa and 1.259 MPa, respectively. Sensitivity analysis of the input random variables reveale that modulus of elasticity of prestressed tendon make most contribution to the pressure capacity of the containment. (C) 2019 Elsevier Ltd. All rights reserved.
机译:核安全壳结构是核电厂最重要的屏蔽结构,该安全壳结构的主要功能是防止事故条件下放射性物质泄漏到环境中,对于了解安全壳的性能具有重要意义。发生严重事故时。本文对严重事故下的预应力混凝土安全壳进行了脆性分析。首先,建立安全壳的详细三维有限元模型,考虑材料的非线性和沿预应力筋的不均匀有效预应力分布。其次,结合MATLAB程序和python脚本,开发了拉丁超立方采样技术,以更新ABAQUS输入文件中的材料参数,以生成30个随机样本。彻底研究了考虑到不确定性和认知不确定性的五个关键位置的脆弱性曲线和具有不同置信度的脆弱性曲线。最后,对输入随机变量进行了敏感性分析,以更好地理解各种随机参数的重要性。结果表明,安全壳的功能失效主要由设备舱口的位置决定。从复合脆性曲线获得的HCLPF压力容量与以95%置信度从脆性曲线获得的安全壳的下限压力容量之间的差异很小。下限压力容量和上限压力容量分别为0.837 MPa和1.259 MPa。输入随机变量的敏感性分析表明,预应力筋的弹性模量对安全壳的抗压能力做出了最大贡献。 (C)2019 Elsevier Ltd.保留所有权利。

著录项

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号