Study on Inelastic Strain-Based Seismic Fragility Analysis for Nuclear Metal Components
The main purpose of this study is to investigate the feasibility of the seismic fragility analysis (FA) with the strain-based failure modes for the nuclear metal components retaining pressure boundary. Through this study, it is expected that we can find analytical ways to enhance the high confidence...
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| Format: | Article |
| Language: | English |
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MDPI AG
2021-06-01
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| Series: | Energies |
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| Online Access: | https://www.mdpi.com/1996-1073/14/11/3269 |
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| author | Gyeong-Hoi Koo Shinyoung Kwag Hyun-Suk Nam |
| author_facet | Gyeong-Hoi Koo Shinyoung Kwag Hyun-Suk Nam |
| author_sort | Gyeong-Hoi Koo |
| collection | DOAJ |
| description | The main purpose of this study is to investigate the feasibility of the seismic fragility analysis (FA) with the strain-based failure modes for the nuclear metal components retaining pressure boundary. Through this study, it is expected that we can find analytical ways to enhance the high confidence of low probability of failure (<i>HCLPF</i>) capacity potentially contained in the conservative seismic design criteria required for the nuclear metal components. Another goal is to investigate the feasibility of the seismic FA to be used as an alternative seismic design rule for beyond-design-basis earthquakes. To do this, the general procedures of the seismic FA using the inelastic seismic analysis for the nuclear metal components are investigated. Their procedures are described in detail by the exampled calculations for the surge line nozzles connecting hot leg piping and the pressurizer, known as one of the seismic fragile components in NSSS (Nuclear Steam Supply System). To define the seismic failure modes for the seismic FA, the seismic strain-based design criteria, with two seismic acceptance criteria against the ductile fracture failure mode and fatigue-induced failure mode, are used in order to reduce the conservatism contained in the conventional stress-based seismic design criteria. In the exampled calculation of the inelastic seismic strain response beyond an elastic regime, precise inelastic seismic analyses with Chaboche’s kinematic and Voce isotropic hardening material models are used. From the results of the seismic FA by the probabilistic approach for the exampled target component, it is confirmed that the approach of the strain-based seismic FA can extract the maximum seismic capacity of the nuclear metal components with more accurate inelastic seismic analysis minimizing the number of variables for the components. |
| first_indexed | 2024-03-10T10:45:11Z |
| format | Article |
| id | doaj.art-ba8b70fd48a34cf9904405b3b103c95c |
| institution | Directory Open Access Journal |
| issn | 1996-1073 |
| language | English |
| last_indexed | 2024-03-10T10:45:11Z |
| publishDate | 2021-06-01 |
| publisher | MDPI AG |
| record_format | Article |
| series | Energies |
| spelling | doaj.art-ba8b70fd48a34cf9904405b3b103c95c2023-11-21T22:40:36ZengMDPI AGEnergies1996-10732021-06-011411326910.3390/en14113269Study on Inelastic Strain-Based Seismic Fragility Analysis for Nuclear Metal ComponentsGyeong-Hoi Koo0Shinyoung Kwag1Hyun-Suk Nam2Korea Atomic Energy Research Institute, Daejeon 34057, KoreaDepartment of Civil and Environmental Engineering, Hanbat National University, Daejeon 34158, KoreaKHNP Central Research Institute, Daejeon 305-353, KoreaThe main purpose of this study is to investigate the feasibility of the seismic fragility analysis (FA) with the strain-based failure modes for the nuclear metal components retaining pressure boundary. Through this study, it is expected that we can find analytical ways to enhance the high confidence of low probability of failure (<i>HCLPF</i>) capacity potentially contained in the conservative seismic design criteria required for the nuclear metal components. Another goal is to investigate the feasibility of the seismic FA to be used as an alternative seismic design rule for beyond-design-basis earthquakes. To do this, the general procedures of the seismic FA using the inelastic seismic analysis for the nuclear metal components are investigated. Their procedures are described in detail by the exampled calculations for the surge line nozzles connecting hot leg piping and the pressurizer, known as one of the seismic fragile components in NSSS (Nuclear Steam Supply System). To define the seismic failure modes for the seismic FA, the seismic strain-based design criteria, with two seismic acceptance criteria against the ductile fracture failure mode and fatigue-induced failure mode, are used in order to reduce the conservatism contained in the conventional stress-based seismic design criteria. In the exampled calculation of the inelastic seismic strain response beyond an elastic regime, precise inelastic seismic analyses with Chaboche’s kinematic and Voce isotropic hardening material models are used. From the results of the seismic FA by the probabilistic approach for the exampled target component, it is confirmed that the approach of the strain-based seismic FA can extract the maximum seismic capacity of the nuclear metal components with more accurate inelastic seismic analysis minimizing the number of variables for the components.https://www.mdpi.com/1996-1073/14/11/3269nuclear componentseismic fragility analysisseismic capacity<i>HCLPF</i>strain-based seismic criteriaductile fracture |
| spellingShingle | Gyeong-Hoi Koo Shinyoung Kwag Hyun-Suk Nam Study on Inelastic Strain-Based Seismic Fragility Analysis for Nuclear Metal Components Energies nuclear component seismic fragility analysis seismic capacity <i>HCLPF</i> strain-based seismic criteria ductile fracture |
| title | Study on Inelastic Strain-Based Seismic Fragility Analysis for Nuclear Metal Components |
| title_full | Study on Inelastic Strain-Based Seismic Fragility Analysis for Nuclear Metal Components |
| title_fullStr | Study on Inelastic Strain-Based Seismic Fragility Analysis for Nuclear Metal Components |
| title_full_unstemmed | Study on Inelastic Strain-Based Seismic Fragility Analysis for Nuclear Metal Components |
| title_short | Study on Inelastic Strain-Based Seismic Fragility Analysis for Nuclear Metal Components |
| title_sort | study on inelastic strain based seismic fragility analysis for nuclear metal components |
| topic | nuclear component seismic fragility analysis seismic capacity <i>HCLPF</i> strain-based seismic criteria ductile fracture |
| url | https://www.mdpi.com/1996-1073/14/11/3269 |
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