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引用次数: 0
摘要
本研究旨在研究预应力混凝土安全壳在结构失效模式试验非线性有限元(FE)分析下的承载能力。首先,在常温条件下评估了三种候选结构失效标准的适用性,结果表明,基于最大主应变的结构失效标准预测的极限承压能力(UPC)与试验数据最为接近。研究了温度升高对假定的严重事故诱发条件的影响,根据不同的失效标准,在峰值温度 200 °C 时,UPC 的降低率约为 1.19-1.49%。最后,进行了置信度为 95% 的参数 FE 分析,以量化材料特性不确定性的影响。总体而言,混凝土和钢筋的材料特性改变的影响大于肌腱预应力的影响,在上限情况下 UPC 的增加超过了下限情况下 UPC 的减少。
Investigation on structural failure criteria and material property uncertainties of prestressed concrete containment structure
This study is to examine load-carrying capacity of a prestressed concrete containment vessel under the structural failure mode test non-linear finite element (FE) analyses. Firstly, suitability of three candidate structural failure criteria was evaluated at ambient temperature condition, of which results showed that the maximum principal strain-based one predicts ultimate pressure capacity (UPC) most closely with the test data. Effect of increasing temperature corresponding to a postulated severe accident-induced condition was investigated and the UPC exhibited reduction ratios of 1.19–1.49% at the peak temperature of 200 °C approximately depending on each failure criterion. Finally, parametric FE analyses at 95% confidence level were performed to quantify effect of material property uncertainties. Overall, the impact of altered material properties of concrete and rebar was higher than that of tendon prestress, and the increase of UPC in upper bound cases exceeded the decrease of UPC in lower bound cases.
期刊介绍:
Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters.
NET covers all fields for peaceful utilization of nuclear energy and radiation as follows:
1) Reactor Physics
2) Thermal Hydraulics
3) Nuclear Safety
4) Nuclear I&C
5) Nuclear Physics, Fusion, and Laser Technology
6) Nuclear Fuel Cycle and Radioactive Waste Management
7) Nuclear Fuel and Reactor Materials
8) Radiation Application
9) Radiation Protection
10) Nuclear Structural Analysis and Plant Management & Maintenance
11) Nuclear Policy, Economics, and Human Resource Development