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Integrity assessment of grouted posttensioning cables and reinforced concrete of a nuclear containment building

机译:核安全壳建筑物注浆后张电缆和钢筋混凝土的完整性评估

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The Containment Buildings of CANDU Nuclear Generating Stations were designed to house nuclear reactors and process equipment and also to provide confinement of releases from a potential nuclear accident such as a Loss Of Coolant Accident?(LOCA). To meet this design requirement, a post-tensioning system was designed to induce compressive stresses in the structure to counteract the internal design pressure. The CANDU reactor building at Gentilly-1?(G-1), Quebec,?Canada?(250?MWe) was built in the early?1970s and is currently in a decommissioned state. The structure at present is under surveillance and monitoring. In the year 2000, a field investigation was conducted as part of a condition assessment and corrosion was detected in some of the grouted post-tension cable strands. However, no further work was done at that time to determine the cause, nature, impact and extent of the corrosion. An investigation of the Gentilly-1 containment building is currently underway to assess the condition of grouted post-tensioning cables and reinforced concrete. At two selected locations, concrete and steel reinforcements were removed from the containment building wall to expose horizontal cables. Individual cable strands and reinforcement bars were instrumented and measurements were taken in-situ before removing them for forensic examination and destructive testing to determine the impact of ageing and corrosion. Concrete samples were also removed and tested in a laboratory. The purpose of the field investigation and laboratory testing, using this structure as a test bed, was also to collect material ageing data and to develop potential Nondestructive Examination?(NDE) methods to monitor Containment Building Integrity. The paper describes the field work conducted and the test results obtained for concrete, reinforcement and post-tensioning cables.
机译:CANDU核电站的安全壳设计用来容纳核反应堆和过程设备,并限制可能的核事故(如冷却液损失事故?)的释放。为了满足此设计要求,设计了后张紧系统以在结构中引起压缩应力以抵消内部设计压力。位于魁北克省的Gentilly-1(G-1),加拿大(250MWe)的CANDU反应堆大楼建于1970年代初期,目前处于退役状态。目前的结构正在受到监视和监视。在2000年,作为状态评估的一部分进行了现场调查,并发现了一些注浆后张力电缆束中的腐蚀。但是,当时没有做进一步的工作来确定腐蚀的原因,性质,影响和程度。目前正在进行Gentilly-1安全壳建筑的调查,以评估注浆后张拉电缆和钢筋混凝土的状况。在两个选定的位置,将混凝土和钢筋从收容建筑的墙壁上移开,露出水平电缆。对单个的电缆束和钢筋进行仪器检测,并在将其移出之前进行现场测量,以进行法医检查和破坏性测试,以确定老化和腐蚀的影响。还取出了混凝土样品并在实验室中进行了测试。使用此结构作为测试台,进行现场调查和实验室测试的目的还在于收集材料的老化数据,并开发潜在的无损检测方法(NDE)来监控建筑物的完整性。本文描述了混凝土,钢筋和后张拉电缆进行的现场工作以及获得的测试结果。

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