核电厂安全壳结构模型碳纤维布加固试验研究  

EXPERIMENTAL STUDY OF NUCLEAR POWER PLANT CONCRETE CONTAINMENT STRENGTHENED WITH EXTERNALLY WRAPPED CARBON FIBER REINFORCED POLYMER SHEETS

作　　者：阳涛[1] 杨哲飚 陆新征[2] 陈文永[1] 丁一[1] 

机构地区：[1]中冶建筑研究总院有限公司,北京100088 [2]清华大学土木工程安全与耐久教育部重点试验室,北京100084

出　　处：《工程力学》2017年第8期144-153,共10页Engineering Mechanics

基　　金：国家科技重大专项经费项目(2012ZX06004-012)

摘　　要：核电站安全壳是防止核泄漏的最后安全屏障。该文基于某核电厂预应力安全壳的1∶10结构模型,开展试验研究。利用内部水压来模拟事故中安全壳的压力,试验通过数百个传感器和数据采集系统详细测得安全壳各部位的受力过程。在试验中,先加载至结构破坏,然后采用外包碳纤维布的方式进行加固并再次加载试验。在ANSYS中建立了安全壳模型的有限元模型进行分析,试验和计算结果表明CFRP加固能够显著提高安全壳结构的承压能力,同时也能有效控制安全壳结构的变形和裂缝发展。有限元计算分析结果与试验结果吻合良好,能够用来预测碳纤维布加固后结构的表现。Concrete containment of nuclear power plant is the final shield structure in case of nuclear leakage during an accident. A 1/10 scaled model of a prestressed concrete containment was studied in this work. The model containment was loaded by internal hydraulic pressure which simulated the design pressure during the accident. Hundreds of sensors and data-collect systems were used in the experiment to measure the response of the containment. The containment was first loaded to the damage pressure and then strengthened with externally wrapping carbon fiber reinforced polymer （CFRP） sheet around the external surface of the containment. Nonlinear finite element analysis model was established using ANSYS to analyze the performance of the strengthened structure. Both experimental and finite element analysis results indicate that the CFRP sheets are able to not only increase the capacity of concrete containment to resist the internal pressure, but also restraint the deformation and crack propagation effectively. The finite element model generates good agreements with the test results, which can be used to predict the performance of containment which is strengthened with CFRP sheets.

关 键 词：碳纤维布 安全壳 加固 承压能力 裂缝 

分 类 号：TU311[建筑科学—结构工程] P315.9[天文地球—地震学]