Seismic fragility of RC shear walls in nuclear power plant Part 1: Characterization of uncertainty in concrete constitutive model

2015 ◽  
Vol 295 ◽  
pp. 576-586 ◽  
Author(s):  
Sammiuddin Syed ◽  
Abhinav Gupta
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Constitutive Model ◽  
Nuclear Power ◽  
Shear Walls ◽  
Plant Part ◽  
Seismic Fragility

scholarly journals 601 Development for Scismic lsolation Engineering of Nuclear Power Plant (Part 1) : Tri-axial Shaking Table Test of the Scale-down Main Steam Piping Model

2013 ◽  
Vol 2013.21 (0) ◽  
pp. 35-36
Author(s):  
Teruyoshi OTOYO ◽  
Akihito OTANI ◽  
Keisuke SASAJIMA ◽  
Hideo HIRAI ◽  
Hirohide IIIZUMI ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Shaking Table Test ◽  
Plant Part ◽  
Shaking Table ◽  
Scale Down ◽  
Main Steam

Multi-objective-based seismic fragility relocation for a Korean nuclear power plant

2020 ◽  
Vol 103 (3) ◽  
pp. 3633-3659 ◽  
Author(s):  
Shinyoung Kwag ◽  
Daegi Hahm
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Seismic Fragility ◽  
Multi Objective

A Unified Constitutive Model With Optimized Parameters for Base and Diffusion Bonded Alloy 800H

2020 ◽  
Author(s):  
Heramb P. Mahajan ◽  
Tasnim Hassan
Keyword(s):  
Elevated Temperature ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Constitutive Model ◽  
Nuclear Power ◽  
Parameter Determination ◽  
Alloy 800H ◽  
Inelastic Analysis ◽  
Creep Fatigue ◽  
Plant Components

Abstract Current ASME Section III, Division 5 code provides elastic, simplified inelastic and inelastic analysis options for designing nuclear power plant components for elevated temperature service. These analyses methods may fail to capture the complex creep-fatigue response and damage accumulation in materials at elevated temperatures. Hence, for analysis and design of the nuclear power plant components at elevated temperature, a full inelastic analysis that can simulate creep-fatigue responses may be needed. Existing ASME code neither provides guidelines for using full inelastic analysis nor recommends the type of constitutive model to be used. Hence, a unified rate-dependent constitutive model incorporating a damage parameter will be developed, and its parameters for base metal will be determined. In addition, a full inelastic analysis methodology using this model to analyze the creep-fatigue performance of components for nuclear power applications will be developed. Base metal 800H (BM800H) data are collected from literature to determine constitutive material model parameters. The parameter determination methodology for a constitutive model is discussed. The optimized parameter set for BM 800H at different temperatures will be presented in the paper. Recommendations are provided on the constitutive model selection and its parameter determination techniques. In the future, this work will be continued for diffusion bonded Alloy 800H (DB800H) material, and obtained parameters will be compared.

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