Identification of Ductile Damage Parameters
Identifikátory výsledku
Kód výsledku v IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21220%2F13%3A00242791" target="_blank" >RIV/68407700:21220/13:00242791 - isvavai.cz</a>
Nalezeny alternativní kódy
RIV/68407700:21220/13:00242794
Výsledek na webu
<a href="http://www.3ds.com/fileadmin/PRODUCTS/SIMULIA/PDF/scc-papers/identification-of-ductile-damage-parameters-13.pdf" target="_blank" >http://www.3ds.com/fileadmin/PRODUCTS/SIMULIA/PDF/scc-papers/identification-of-ductile-damage-parameters-13.pdf</a>
DOI - Digital Object Identifier
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Alternativní jazyky
Jazyk výsledku
angličtina
Název v původním jazyce
Identification of Ductile Damage Parameters
Popis výsledku v původním jazyce
paper describes the calibration process for uncoupled material model of ductile damage by Johnson-Cook and Rice-Tracey that is implemented in FE package Abaqus. As the work was supported by the grant “Identification of ductile damage parameters for nuclear facilities”, calibration was done for typical steel used in nuclear power plant industry. The project includes both design and realization of experiments, and application of experimental outputs in calibration process of material constants of mentioned ductile damage models. Calibration process of material model uses fifteen types of experimental specimens corresponding with literature. The result of the calibration process was verified through the comparison of FE simulation of each specimen with experimental response. As the material model describing ductile damage within the wide range of stress states was searched in this project, the model was tested on a several another specimens which exhibit higher stress concentration.
Název v anglickém jazyce
Identification of Ductile Damage Parameters
Popis výsledku anglicky
paper describes the calibration process for uncoupled material model of ductile damage by Johnson-Cook and Rice-Tracey that is implemented in FE package Abaqus. As the work was supported by the grant “Identification of ductile damage parameters for nuclear facilities”, calibration was done for typical steel used in nuclear power plant industry. The project includes both design and realization of experiments, and application of experimental outputs in calibration process of material constants of mentioned ductile damage models. Calibration process of material model uses fifteen types of experimental specimens corresponding with literature. The result of the calibration process was verified through the comparison of FE simulation of each specimen with experimental response. As the material model describing ductile damage within the wide range of stress states was searched in this project, the model was tested on a several another specimens which exhibit higher stress concentration.
Klasifikace
Druh
O - Ostatní výsledky
CEP obor
JL - Únava materiálu a lomová mechanika
OECD FORD obor
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Návaznosti výsledku
Projekt
<a href="/cs/project/FR-TI2%2F279" target="_blank" >FR-TI2/279: *Identifikace parametrů tvárného porušení materiálů jaderných zařízení</a><br>
Návaznosti
P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)
Ostatní
Rok uplatnění
2013
Kód důvěrnosti údajů
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů