The sensitivity analysis of the dynamic response of reactor coolant system to the input parameters is an important precondition for the design optimization. In this paper, the sensitivity of the dynamic response of reactor coolant system under seismic conditions is analyzed with an integrated platform called OPTIMUS, taking the stiffness of the dampers supporting the steam generator and the main pump as the input variables. Some input parameters of the reactor system are usually different from the design value due to the calculation error, random and other uncontrollable errors in the manufacturing and installation process. In a nuclear power project, the measured stiffness  of the dampers which support the steam generator and the main pump in the manufacturer are deviated from the requirements in the equipment specification, and it is necessary to evaluate the influence of the deviation on the dynamic response analysis of the reactor system. According to the traditional method, it is necessary to establish the models of the reactor coolant system for nonlinear analysis according to the different stiffness  of the dampers, and then the calculation results are compared by EXCEL. In this paper, the sensitivity analysis of output parameters which are the loads at the nozzles of the equipment to the input parameters which are the stiffness of the dampers supporting the steam generator and pump is realized by OPTIMUS, which is a kind of integration platform. Not only can ANSYS simulation calculations be carried out automatically on the OPTIMUS, but also the output data can be processed rapidly automatically, and the influence of manufacturing deviation of the stiffness on the dynamic response of the reactor coolant system can be analyzed quantitatively in the above-mentioned problems, and the data support is provided for the determination of the design variables in subsequent optimization analysis.


Sensitivity Analysis for Dynamical Response of Reactor Coolant System Based on Optimus

Division / Sponsors: 
Power Division & Nuclear Engineering Division (NED)

Power Conference
Paper Proceedings: https://asmedigitalcollection.asme.org/POWER/POWER2020/volume/83747

International Conference on Nuclear Engineering
Paper Proceedings: https://asmedigitalcollection.asme.org/ICONE/ICONE2020/volume/83761

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