LAPSE:2023.34592
Published Article

LAPSE:2023.34592
Evaluation of the Limit State of a Six-Inch Carbon Steel Pipe Elbow in Base-Isolated Nuclear Power Plants
April 27, 2023
Abstract
The installation of base isolation systems in nuclear power plants can improve their safety from seismic loads. However, nuclear power plants with base isolation systems experience greater displacement as they handle seismic loads. The increase in relative displacement is caused by the installed base isolation systems, which increase the seismic risk of the interface piping system. It was found that the failure mode of the interface piping system was low-cycle fatigue failure accompanied by ratcheting, and the fittings (elbows and tees) failed due to the concentration of nonlinear behavior. Therefore, in this study, the limit state was defined as leakage, and an in-plane cyclic loading test was conducted in order to quantitatively express the failure criteria for the SCH40 6-inch carbon steel pipe elbow due to low-cycle fatigue failure. The leakage line and low-cycle fatigue curves of the SCH40 6-inch carbon steel pipe elbow were presented based on the test results. In addition, the limit state was quantitatively expressed using the damage index, based on the combination of ductility and energy dissipation. The average values of the damage index for the 6-inch pipe elbow calculated using the force−displacement (P−D) and moment−relative deformation angle (M−R) relationships were found to be 10.91 and 11.27, respectively.
The installation of base isolation systems in nuclear power plants can improve their safety from seismic loads. However, nuclear power plants with base isolation systems experience greater displacement as they handle seismic loads. The increase in relative displacement is caused by the installed base isolation systems, which increase the seismic risk of the interface piping system. It was found that the failure mode of the interface piping system was low-cycle fatigue failure accompanied by ratcheting, and the fittings (elbows and tees) failed due to the concentration of nonlinear behavior. Therefore, in this study, the limit state was defined as leakage, and an in-plane cyclic loading test was conducted in order to quantitatively express the failure criteria for the SCH40 6-inch carbon steel pipe elbow due to low-cycle fatigue failure. The leakage line and low-cycle fatigue curves of the SCH40 6-inch carbon steel pipe elbow were presented based on the test results. In addition, the limit state was quantitatively expressed using the damage index, based on the combination of ductility and energy dissipation. The average values of the damage index for the 6-inch pipe elbow calculated using the force−displacement (P−D) and moment−relative deformation angle (M−R) relationships were found to be 10.91 and 11.27, respectively.
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Keywords
carbon steel pipe elbow, interface piping system, limit state, low-cycle fatigue, nuclear power plant
Subject
Suggested Citation
Kim SW, Yun DW, Jeon BG, Hahm DG, Kim MK. Evaluation of the Limit State of a Six-Inch Carbon Steel Pipe Elbow in Base-Isolated Nuclear Power Plants. (2023). LAPSE:2023.34592
Author Affiliations
Kim SW: Seismic Research and Test Center, Pusan National University, 49 Busandaehak-ro, Yangsan 50612, Korea [ORCID]
Yun DW: Seismic Research and Test Center, Pusan National University, 49 Busandaehak-ro, Yangsan 50612, Korea
Jeon BG: Seismic Research and Test Center, Pusan National University, 49 Busandaehak-ro, Yangsan 50612, Korea [ORCID]
Hahm DG: Smart Structural Safety & Prognosis Division, Korea Atomic Energy Research Institute, 111 Daedeok-daero, 989 beon-gil, Yusung-gu, Daejon 34057, Korea
Kim MK: Smart Structural Safety & Prognosis Division, Korea Atomic Energy Research Institute, 111 Daedeok-daero, 989 beon-gil, Yusung-gu, Daejon 34057, Korea
Yun DW: Seismic Research and Test Center, Pusan National University, 49 Busandaehak-ro, Yangsan 50612, Korea
Jeon BG: Seismic Research and Test Center, Pusan National University, 49 Busandaehak-ro, Yangsan 50612, Korea [ORCID]
Hahm DG: Smart Structural Safety & Prognosis Division, Korea Atomic Energy Research Institute, 111 Daedeok-daero, 989 beon-gil, Yusung-gu, Daejon 34057, Korea
Kim MK: Smart Structural Safety & Prognosis Division, Korea Atomic Energy Research Institute, 111 Daedeok-daero, 989 beon-gil, Yusung-gu, Daejon 34057, Korea
Journal Name
Energies
Volume
14
Issue
24
First Page
8400
Year
2021
Publication Date
2021-12-13
ISSN
1996-1073
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PII: en14248400, Publication Type: Journal Article
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LAPSE:2023.34592
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https://doi.org/10.3390/en14248400
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