Feasibility Study on Strain-Based Seismic Design Criteria for Nuclear Components

In this paper, the feasibility study to develop strain-based seismic design criteria applicable for the components of nuclear power plants are carried out as an alternative rule to the current stress-based criteria. To do this, two acceptance criteria are investigated through the detailed example of...

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Main Authors: Gyeong-Hoi Koo, Jong-Sung Kim, Yun-Jae Kim
Format: Article
Language:English
Published: MDPI AG 2020-08-01
Series:Energies
Subjects:
Online Access:https://www.mdpi.com/1996-1073/13/17/4435
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author Gyeong-Hoi Koo
Jong-Sung Kim
Yun-Jae Kim
author_facet Gyeong-Hoi Koo
Jong-Sung Kim
Yun-Jae Kim
author_sort Gyeong-Hoi Koo
collection DOAJ
description In this paper, the feasibility study to develop strain-based seismic design criteria applicable for the components of nuclear power plants are carried out as an alternative rule to the current stress-based criteria. To do this, two acceptance criteria are investigated through the detailed example of an application for the surge line nozzles in a nuclear steam supply system, which are known as one of the seismic fragile components in nuclear power plants. These strain-based seismic design criteria are primarily to prevent two types of failure modes, such as a ductile fracture and a cyclic fatigue-induced damage due to continuous large amplitude cyclic loads during seismic event. Through the example problem, the required procedures are described step-by-step with calculations of an accumulated plastic strain, triaxiality factor by the elasto-plastic seismic analysis using the finite element method. For a precise inelastic seismic analysis, the Chaboche kinematic and Voce isotropic hardening material parameters are identified by the test data and used for an inelastic material model. The results by the strain-based criteria are compared with those by the ASME (American Society of Mechanical Engineers) stress-based design criteria for a service level D limits. From the study, it is expected that the strain-based seismic design method investigated in this paper will be beneficial for the nuclear components, especially when the design basis earthquakes are large enough to cause severe plastic strains at a critical location.
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spelling doaj.art-9775deb0975e4ef894676562bfb4d75e2023-11-20T11:37:18ZengMDPI AGEnergies1996-10732020-08-011317443510.3390/en13174435Feasibility Study on Strain-Based Seismic Design Criteria for Nuclear ComponentsGyeong-Hoi Koo0Jong-Sung Kim1Yun-Jae Kim2Korea Atomic Energy Research Institute, Daejeon 34057, KoreaDepartment of Nuclear Engineering, Sejong University, Seoul 05006, KoreaSchool of Mechanical Engineering, Korea University, Seoul 02841, KoreaIn this paper, the feasibility study to develop strain-based seismic design criteria applicable for the components of nuclear power plants are carried out as an alternative rule to the current stress-based criteria. To do this, two acceptance criteria are investigated through the detailed example of an application for the surge line nozzles in a nuclear steam supply system, which are known as one of the seismic fragile components in nuclear power plants. These strain-based seismic design criteria are primarily to prevent two types of failure modes, such as a ductile fracture and a cyclic fatigue-induced damage due to continuous large amplitude cyclic loads during seismic event. Through the example problem, the required procedures are described step-by-step with calculations of an accumulated plastic strain, triaxiality factor by the elasto-plastic seismic analysis using the finite element method. For a precise inelastic seismic analysis, the Chaboche kinematic and Voce isotropic hardening material parameters are identified by the test data and used for an inelastic material model. The results by the strain-based criteria are compared with those by the ASME (American Society of Mechanical Engineers) stress-based design criteria for a service level D limits. From the study, it is expected that the strain-based seismic design method investigated in this paper will be beneficial for the nuclear components, especially when the design basis earthquakes are large enough to cause severe plastic strains at a critical location.https://www.mdpi.com/1996-1073/13/17/4435seismic designstrain-based criteriaaccumulated plastic straintriaxiality factorductile fracturefatigue-induced damage
spellingShingle Gyeong-Hoi Koo
Jong-Sung Kim
Yun-Jae Kim
Feasibility Study on Strain-Based Seismic Design Criteria for Nuclear Components
Energies
seismic design
strain-based criteria
accumulated plastic strain
triaxiality factor
ductile fracture
fatigue-induced damage
title Feasibility Study on Strain-Based Seismic Design Criteria for Nuclear Components
title_full Feasibility Study on Strain-Based Seismic Design Criteria for Nuclear Components
title_fullStr Feasibility Study on Strain-Based Seismic Design Criteria for Nuclear Components
title_full_unstemmed Feasibility Study on Strain-Based Seismic Design Criteria for Nuclear Components
title_short Feasibility Study on Strain-Based Seismic Design Criteria for Nuclear Components
title_sort feasibility study on strain based seismic design criteria for nuclear components
topic seismic design
strain-based criteria
accumulated plastic strain
triaxiality factor
ductile fracture
fatigue-induced damage
url https://www.mdpi.com/1996-1073/13/17/4435
work_keys_str_mv AT gyeonghoikoo feasibilitystudyonstrainbasedseismicdesigncriteriafornuclearcomponents
AT jongsungkim feasibilitystudyonstrainbasedseismicdesigncriteriafornuclearcomponents
AT yunjaekim feasibilitystudyonstrainbasedseismicdesigncriteriafornuclearcomponents