Modal Characteristic Analysis of the Apr1400 Nuclear Reactor Internals for Seismic Analysis

Park, Jong Beom; Choi, Youngin; Lee, Sang Jeong; Park, No Cheol; Park, Kyoung Su; Park, Young Pil; Park, Chan Il

doi:10.5516/net.09.2014.017

Cited by 23 publications

(7 citation statements)

References 11 publications

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“…Here, we focus on the cylindrical structures in the APR1400 internals, and other components are simplified. In the FEA, we validated the FE model using the experimental data for a scaled-down model [1]. The model reduction method was applied to these FE models with various boundary conditions.…”

Section: Application To Apr1400 Reactor Internals 41 Apr1400 Reactomentioning

confidence: 99%

“…The finite element method (FEM) is widely used in vibrational analysis, and the accuracy of the results depends on the quality of the model. Park et al recently described FE models of reactor internals using a scaled-down model and provided an experimental verification of the technique [1]. Although these FE models provide accurate results, the complex structural form of the reactor internals and the fluid elements used to describe the fluid-structure interaction (FSI) leads to a large number of elements and nodes, which in turn leads to significant computational expense.…”

Section: Introductionmentioning

confidence: 98%

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Model reduction methods for cylindrical structures in reactor internals considering the fluid–structure interaction

Choi

Park

Lee

et al. 2015

Journal of Nuclear Science and Technology

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Vibrational analysis of the complex structure of reactor internals using the finite element method leads to considerable computational expense. Additionally, fluid-structure interaction (FSI) effects due to liquid coolant result in a large number of fluid elements. Here, we describe a model reduction method based on Guyan theory to solve these complex numerical problems efficiently. The master degrees of freedom selection process, which is based on the shapes of vibrational modes, is discussed. We consider the structural characteristics of the cylindrical parts of the reactor, and include FSI effects. To verify the model reduction method, several numerical examples of simple cylindrical shells are described with and without the coolant. Practical application to the internals of an advanced pressurized reactor 1400 (APR1400) is discussed with various different conditions. Keywords: model reduction method; Guyan reduction; master degrees of freedom selection; reactor internals; fluid-structure interaction IntroductionVibrational analysis is an important aspect of structural integrity assessments of nuclear reactors, and it can be used to identify the response of the reactor internals to vibration sources such as earthquakes and flowinduced vibrations. The finite element method (FEM) is widely used in vibrational analysis, and the accuracy of the results depends on the quality of the model. Park et al. recently described FE models of reactor internals using a scaled-down model and provided an experimental verification of the technique [1]. Although these FE models provide accurate results, the complex structural form of the reactor internals and the fluid elements used to describe the fluid-structure interaction (FSI) leads to a large number of elements and nodes, which in turn leads to significant computational expense. For this reason, Choi et al. constructed a simplified FE model of reactor internals using one-dimensional elements and reported computationally efficient seismic analyses [2]. However, the use of such a simplified model has significant limitations in terms of the geometry.Recently, model reduction methods have been reported to reduce the overall computational costs, with applications in fields, including automobiles, aircraft,

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Section: Application To Apr1400 Reactor Internals 41 Apr1400 Reactomentioning

confidence: 99%

Section: Introductionmentioning

confidence: 98%

Model reduction methods for cylindrical structures in reactor internals considering the fluid–structure interaction

Choi

Park

Lee

et al. 2015

Journal of Nuclear Science and Technology

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“…In addition, detailed features which cause geometrical nonlinearities, such as the outlet nozzle on the CSB barrel, also are represented in the FE model. The developed FE model of the RVI is represented in Figure 2 [16]. The overall procedures of the FE analysis are performed with the commercial FE analysis software ANSYS (version 16.0) [18].…”

Section: Finite Element Modeling and Dynamic Characteristicsmentioning

confidence: 99%

“…To verify the validity of the FE model, the experimental dynamic characteristics extracted from the scaled-down model are used. The detailed procedures and contents are descripted in reference [16]. Figure 3 shows the extracted mode shapes of the important eigenmodes against the seismic excitation which have large effective mass.…”

Section: Finite Element Modeling and Dynamic Characteristicsmentioning

confidence: 99%

“…In this paper, the seismic responses of the RVI in the advanced power reactor 1400 (APR1400) are numerically identified using the FE method. The previously developed 3-D detailed FE model, which verified its validity with the experimental results, is used for the FE analysis [16]. The FE model of the RVI includes numerous number of elements, including fluid elements, thus the model reduction, the fixed-interface CMS method suggested by Craig and Bampton is applied to reduce the total computation costs [11].…”

Section: Introductionmentioning

confidence: 99%

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Seismic analysis of the APR 1400 reactor vessel internals using the model reduction method

Choi

Park

Lee

et al. 2016

Journal of Nuclear Science and Technology

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To secure reliability of the seismic design of the reactor vessel internals (RVIs) through the finite element analysis, it is important to develop the accurate analysis model which can represent the geometric complexity of the RVIs. However, the seismic analysis requires too large computation cost to solve the complex equations; thus, it needs to reduce the overall size of the analysis model. Here, we apply a model reduction method based on the fixed-interface component mode synthesis (CMS) method to practical RVIs to solve complex numerical problems efficiently. To verify the model reduction method, several cases of the RVIs with different conditions are analyzed for the static and dynamic problems. Finally, the seismic analysis was performed with the suggested reduced model with the CMS method. The time history analysis is performed to extract important seismic responses at the specified locations, and the stress analysis is also performed to identify that the RVIs satisfy the seismic design. In the last part of the paper, an example of the design modification is suggested to reduce the stress intensity at the support locations.

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Calculation of coupled added mass of multibody system immersed in fluids

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Modal Characteristic Analysis of the Apr1400 Nuclear Reactor Internals for Seismic Analysis

Cited by 23 publications

References 11 publications

Model reduction methods for cylindrical structures in reactor internals considering the fluid–structure interaction

Model reduction methods for cylindrical structures in reactor internals considering the fluid–structure interaction

Seismic analysis of the APR 1400 reactor vessel internals using the model reduction method

Calculation of coupled added mass of multibody system immersed in fluids

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