MODELLING STRUCTURE-ANCHOR-COMPONENT INTERACTION FOR NUCLEAR SAFETY RELATED STRUCTURES UNDER SEISMIC LOADS - PART 1: GENERATION OF EXPERIMENTAL DATABASE

摘要

In Nuclear Power Plants (NPP) and related facilities, the structure-component interaction in event of an earthquake depends on the behaviour of concrete structure, component and anchorage system connecting the two. Currently, due to the lack of models for simulating the inelastic anchorage behaviour, the connection between a component (such as a piping) and the structure is considered as rigid, which is unrealistic and non-conservative. In this work, it is attempted to develop a relatively simple and realistic macro spring model for the post-installed anchors connecting the components to RC structure. This paper presents the results of a series of experiments performed on the anchors to generate the required database for the development of the model. Two different types of undercut anchors that are qualified for the application in NPP are tested under the program following the recommendations of German guideline for anchorages in nuclear power plants (DIBt, 2010). The testing program included monotonic and cyclic load tests in non-cracked and cracked concrete specimens with different specified crack widths. These tests provided information on the load-displacement envelop as well as hysteretic behaviour of the anchor at different crack widths. Additionally, crack cycling tests for two different crack width levels were performed to evaluate the influence of crack cycling on displacement behaviour and residual load of the anchors. The evaluation of the test results towards development of numerical models is presented in accompanying paper.