Dynamic characteristics identification of reactor internals in SMART considering fluid-structure interaction

Youngin Choi, Seungho Lim, Byung Han Ko, Kyoung Su Park, No Cheol Park, Young Pil Park, Kyeong Hoon Jeong, Jin Seok Park

Research output: Contribution to journalArticle

27 Citations (Scopus)

Abstract

The System-Integrated Modular Advanced ReacTor (SMART) was developed by the Korea Atomic Energy Research Institute (KAERI). It is an integrated pressurized water reactor which includes most components in only one reactor vessel. In the structural reactor design, vibration assessment is one of the important technology validations in order to prevent damage from seismic loads and flow-induced vibration. This analysis is performed using modal analysis, which includes finite element analysis and modal test, in order to identify the dynamic characteristics of the reactor internals. First, the 1/12 scaled-down model of the reactor internals is designed for modal analysis. The three-dimensional finite element model is constructed using the commercial package ANSYS based on this model. It represents the detailed geometric shape of the reactor internals and also considers the fluid-structure interaction effect caused by the reactor coolant. In order to validate the results of the finite element analysis, the modal test with the scaled-down model is performed. We found that the results from the FEA are well matched with the results of the modal test. From the results, we can extract the dynamic characteristics of the totally assembled reactor internals that are in contact with water and verify the validity of the detailed finite element model of the scaled-down model of the reactor internals. The finite element model can be used to predict the dynamic characteristics of the reactor internals and can be utilized in further research such as seismic analysis and postulated pipe rupture analysis. This paper performs a similarity analysis in order to predict the dynamic characteristics of real reactor internals using the NAVMI factor and correction factors. The results of the similarity analysis correspond well with the results of the FEA.

Original languageEnglish
Pages (from-to)202-211
Number of pages10
JournalNuclear Engineering and Design
Volume255
DOIs
Publication statusPublished - 2013 Jan 1

Fingerprint

fluid-structure interaction
Fluid structure interaction
dynamic characteristics
reactors
fluids
Finite element method
interactions
Modal analysis
Pressurized water reactors
reactor
vibration
Nuclear energy
Coolants
pressurized water reactors
reactor design
Korea
analysis
coolants
Pipe
nuclear energy

All Science Journal Classification (ASJC) codes

  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering
  • Materials Science(all)
  • Safety, Risk, Reliability and Quality
  • Waste Management and Disposal
  • Mechanical Engineering

Cite this

Choi, Youngin ; Lim, Seungho ; Ko, Byung Han ; Park, Kyoung Su ; Park, No Cheol ; Park, Young Pil ; Jeong, Kyeong Hoon ; Park, Jin Seok. / Dynamic characteristics identification of reactor internals in SMART considering fluid-structure interaction. In: Nuclear Engineering and Design. 2013 ; Vol. 255. pp. 202-211.
@article{b0c758b98d064e8780f2c7e4206d1336,
title = "Dynamic characteristics identification of reactor internals in SMART considering fluid-structure interaction",
abstract = "The System-Integrated Modular Advanced ReacTor (SMART) was developed by the Korea Atomic Energy Research Institute (KAERI). It is an integrated pressurized water reactor which includes most components in only one reactor vessel. In the structural reactor design, vibration assessment is one of the important technology validations in order to prevent damage from seismic loads and flow-induced vibration. This analysis is performed using modal analysis, which includes finite element analysis and modal test, in order to identify the dynamic characteristics of the reactor internals. First, the 1/12 scaled-down model of the reactor internals is designed for modal analysis. The three-dimensional finite element model is constructed using the commercial package ANSYS based on this model. It represents the detailed geometric shape of the reactor internals and also considers the fluid-structure interaction effect caused by the reactor coolant. In order to validate the results of the finite element analysis, the modal test with the scaled-down model is performed. We found that the results from the FEA are well matched with the results of the modal test. From the results, we can extract the dynamic characteristics of the totally assembled reactor internals that are in contact with water and verify the validity of the detailed finite element model of the scaled-down model of the reactor internals. The finite element model can be used to predict the dynamic characteristics of the reactor internals and can be utilized in further research such as seismic analysis and postulated pipe rupture analysis. This paper performs a similarity analysis in order to predict the dynamic characteristics of real reactor internals using the NAVMI factor and correction factors. The results of the similarity analysis correspond well with the results of the FEA.",
author = "Youngin Choi and Seungho Lim and Ko, {Byung Han} and Park, {Kyoung Su} and Park, {No Cheol} and Park, {Young Pil} and Jeong, {Kyeong Hoon} and Park, {Jin Seok}",
year = "2013",
month = "1",
day = "1",
doi = "10.1016/j.nucengdes.2012.10.010",
language = "English",
volume = "255",
pages = "202--211",
journal = "Nuclear Engineering and Design",
issn = "0029-5493",
publisher = "Elsevier BV",

}

Dynamic characteristics identification of reactor internals in SMART considering fluid-structure interaction. / Choi, Youngin; Lim, Seungho; Ko, Byung Han; Park, Kyoung Su; Park, No Cheol; Park, Young Pil; Jeong, Kyeong Hoon; Park, Jin Seok.

In: Nuclear Engineering and Design, Vol. 255, 01.01.2013, p. 202-211.

Research output: Contribution to journalArticle

TY - JOUR

T1 - Dynamic characteristics identification of reactor internals in SMART considering fluid-structure interaction

AU - Choi, Youngin

AU - Lim, Seungho

AU - Ko, Byung Han

AU - Park, Kyoung Su

AU - Park, No Cheol

AU - Park, Young Pil

AU - Jeong, Kyeong Hoon

AU - Park, Jin Seok

PY - 2013/1/1

Y1 - 2013/1/1

N2 - The System-Integrated Modular Advanced ReacTor (SMART) was developed by the Korea Atomic Energy Research Institute (KAERI). It is an integrated pressurized water reactor which includes most components in only one reactor vessel. In the structural reactor design, vibration assessment is one of the important technology validations in order to prevent damage from seismic loads and flow-induced vibration. This analysis is performed using modal analysis, which includes finite element analysis and modal test, in order to identify the dynamic characteristics of the reactor internals. First, the 1/12 scaled-down model of the reactor internals is designed for modal analysis. The three-dimensional finite element model is constructed using the commercial package ANSYS based on this model. It represents the detailed geometric shape of the reactor internals and also considers the fluid-structure interaction effect caused by the reactor coolant. In order to validate the results of the finite element analysis, the modal test with the scaled-down model is performed. We found that the results from the FEA are well matched with the results of the modal test. From the results, we can extract the dynamic characteristics of the totally assembled reactor internals that are in contact with water and verify the validity of the detailed finite element model of the scaled-down model of the reactor internals. The finite element model can be used to predict the dynamic characteristics of the reactor internals and can be utilized in further research such as seismic analysis and postulated pipe rupture analysis. This paper performs a similarity analysis in order to predict the dynamic characteristics of real reactor internals using the NAVMI factor and correction factors. The results of the similarity analysis correspond well with the results of the FEA.

AB - The System-Integrated Modular Advanced ReacTor (SMART) was developed by the Korea Atomic Energy Research Institute (KAERI). It is an integrated pressurized water reactor which includes most components in only one reactor vessel. In the structural reactor design, vibration assessment is one of the important technology validations in order to prevent damage from seismic loads and flow-induced vibration. This analysis is performed using modal analysis, which includes finite element analysis and modal test, in order to identify the dynamic characteristics of the reactor internals. First, the 1/12 scaled-down model of the reactor internals is designed for modal analysis. The three-dimensional finite element model is constructed using the commercial package ANSYS based on this model. It represents the detailed geometric shape of the reactor internals and also considers the fluid-structure interaction effect caused by the reactor coolant. In order to validate the results of the finite element analysis, the modal test with the scaled-down model is performed. We found that the results from the FEA are well matched with the results of the modal test. From the results, we can extract the dynamic characteristics of the totally assembled reactor internals that are in contact with water and verify the validity of the detailed finite element model of the scaled-down model of the reactor internals. The finite element model can be used to predict the dynamic characteristics of the reactor internals and can be utilized in further research such as seismic analysis and postulated pipe rupture analysis. This paper performs a similarity analysis in order to predict the dynamic characteristics of real reactor internals using the NAVMI factor and correction factors. The results of the similarity analysis correspond well with the results of the FEA.

UR - http://www.scopus.com/inward/record.url?scp=84871233333&partnerID=8YFLogxK

UR - http://www.scopus.com/inward/citedby.url?scp=84871233333&partnerID=8YFLogxK

U2 - 10.1016/j.nucengdes.2012.10.010

DO - 10.1016/j.nucengdes.2012.10.010

M3 - Article

AN - SCOPUS:84871233333

VL - 255

SP - 202

EP - 211

JO - Nuclear Engineering and Design

JF - Nuclear Engineering and Design

SN - 0029-5493

ER -