Dynamic Analysis of the Control Rod and Fuel Assemblies

摘要

This paper presents a method to analyze the dynamic response during seismic excitations of the important componentsrnof the 200MW Nuclear Heating Reactor (NHR), including the control rod, fuel assemblies, zircaloy boxes and related parts.rnThe analyzed structure is one of thirty-two groups in the whole core. The NHR reactor differs from other reactor typesrnbecause the control rod is driven by hydraulic pressure so intricate fluid-solid coupling occurs which makes the problem morerndifficult. The paper describes appropriate simplifications and the model. The model is then used to calculate the vibrationrnfrequencies, the responses to the frequency spectrum and the transient responses for some seismic excitations.