TY - JOUR
T1 - Investigation of seismic responses of reactor vessel and internals for beyond-design basis earthquake using elasto-plastic time history analysis
AU - Lee, Sang Jeong
AU - Lee, Eun ho
AU - Lee, Changkyun
AU - Park, No Cheol
AU - Choi, Youngin
AU - Oh, Changsik
N1 - Publisher Copyright:
© 2020 Korean Nuclear Society
PY - 2021/3
Y1 - 2021/3
N2 - Existing elastic analysis methods cannot be adhered to in order to assess the structural integrity of a reactor vessel and internals for a beyond design basis earthquake. Elasto-plastic analysis methods are required, and the factors that affect the elasto-plastic behavior of reactor materials should be taken into account. In this study, a material behavior model was developed that considers the irradiation embrittlement effect, which affects the elasto-plastic behavior of the reactor material. This was used to perform the elasto-plastic time history analyses of the reactor vessel and its internals for beyond design basis earthquake. For this investigation, appropriate beyond design basis earthquakes and reliable finite element models were used. Based on the analysis results, consideration was given to the load reduction effect and the margin change. These were transferred to the internals due to the plastic deformation of the reactor vessel.
AB - Existing elastic analysis methods cannot be adhered to in order to assess the structural integrity of a reactor vessel and internals for a beyond design basis earthquake. Elasto-plastic analysis methods are required, and the factors that affect the elasto-plastic behavior of reactor materials should be taken into account. In this study, a material behavior model was developed that considers the irradiation embrittlement effect, which affects the elasto-plastic behavior of the reactor material. This was used to perform the elasto-plastic time history analyses of the reactor vessel and its internals for beyond design basis earthquake. For this investigation, appropriate beyond design basis earthquakes and reliable finite element models were used. Based on the analysis results, consideration was given to the load reduction effect and the margin change. These were transferred to the internals due to the plastic deformation of the reactor vessel.
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U2 - 10.1016/j.net.2020.08.011
DO - 10.1016/j.net.2020.08.011
M3 - Article
AN - SCOPUS:85090859227
SN - 1738-5733
VL - 53
SP - 988
EP - 1003
JO - Nuclear Engineering and Technology
JF - Nuclear Engineering and Technology
IS - 3
ER -