Session: SE-07-01 Seismic Evaluation of Systems, Structures and Components
Paper Number: 107126
107126 - Study on Analysis Procedure Using Integrated Three-Dimensional Fe Model for Reactor Coolant System by Applying to Shaking Table Tests for Scaled Mock-Ups
Generally, seismic stress evaluation for a Class 1 component of a nuclear power plant is performed using Finite Element stress analysis with seismic loads that are obtained another calculation.
In Japan, a multimass beam model is usually employed to calculate seismic loads for components in a reactor coolant system (RCS) of PWR plant. The components are modeled into simple elements such as mass points and beams in the multimass beam model.
So far, three-dimensional FE analysis (3D-FEA) has been applied to stress analysis for each portion in a component. Recent advances in computer performance, however, have made large-scale analysis possible, and 3D-FEA for not only whole of a component but also the integrated all components in a RCS is not difficult at the present time.
If the integrated whole 3D-FE model of RCS is employed, stress due to seismic can be directly calculated by applying seismic waves to the 3D-FE model, and the multimass beam model is not necessary.
So, we are developing a stress evaluation method that uses an integrated 3D-FE model consisted of all components in RCS, which is called “Seamless Structural Analysis Process”.
As a validation for this method, this method has been applied to the shaking table tests for scaled mock-ups previously conducted by the Japanese national projects and the results are discussed in this paper.
Three scaled mock-ups, which were modeled for reactor coolant system (RCS), reactor vessel (RV) and reactor vessel internal/control rod drive mechanism (RVI/CRDM), were prepared for these projects.
In our study, 3D-FE models have been developed for the RCS, RV and RVI/CRDM mock-ups, and time history response analyses have been performed for those 3D-FE models. The results are discussed in this paper.
Presenting Author: Yasutaka Kumagai Mitsubishi Heavy Industry
Presenting Author Biography: 2007 Mar M.S Osaka Electro-Communication University
2007 April I joined Mitsubishi Heavy industry
I am in charge of designing Reactor internal.
Authors:
Takehiro Kawashima Mitsubishi Heavy IndustryYasutaka Kumagai Mitsubishi Heavy Industry
Yuki Asao Mitsubishi Heavy Industry
Shota Shimazu Mitsubishi Heavy Industry
Takuya Nishimura Mitsubishi Heavy Industry
Study on Analysis Procedure Using Integrated Three-Dimensional Fe Model for Reactor Coolant System by Applying to Shaking Table Tests for Scaled Mock-Ups
Paper Type
Technical Paper Publication