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    Reliability Analysis of the Ductile Fracture of Overpacks for High-Level Radioactive Waste in Repository Conditions

    Source: ASCE-ASME Journal of Risk and Uncertainty in Engineering Systems, Part A: Civil Engineering:;2021:;Volume ( 007 ):;issue: 002::page 04021010-1
    Author:
    A. Persoons
    ,
    J. Serveaux
    ,
    P. Beaurepaire
    ,
    C. Labergere
    ,
    A. Chateauneuf
    ,
    K. Saanouni
    ,
    F. Bumbieler
    DOI: 10.1061/AJRUA6.0001121
    Publisher: ASCE
    Abstract: In France, a deep geological repository project is under development for radioactive waste management. The lack of knowledge from similar facilities and the large time scales involved result in uncertainties about the repository environment in operating conditions. The reliability methods are dedicated to dealing with such problematics and are used in this work to study the behavior of the overpack containing high-level radioactive waste. Its function is to isolate the waste from the environment for the first 500  years. The analysis is based on a finite-element model of the system integrating the time-related degradation of the system and considers a ductile fracture criterion. The stochastic structural model includes uncertain and time dependent corrosion rates and mechanical loading. A Kriging metamodel is calibrated in order to predict the behavior of the finite-element model with a much smaller computation time. The failure probability of the system is estimated using Monte Carlo simulations based on the results of both the finite-element model and the Kriging metamodel. The behavior of the system and the parameters having a first order influence on its performances are investigated through a sensitivity analysis.
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      Reliability Analysis of the Ductile Fracture of Overpacks for High-Level Radioactive Waste in Repository Conditions

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    • ASCE-ASME Journal of Risk and Uncertainty in Engineering Systems, Part A: Civil Engineering

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    contributor authorA. Persoons
    contributor authorJ. Serveaux
    contributor authorP. Beaurepaire
    contributor authorC. Labergere
    contributor authorA. Chateauneuf
    contributor authorK. Saanouni
    contributor authorF. Bumbieler
    date accessioned2022-01-31T23:58:56Z
    date available2022-01-31T23:58:56Z
    date issued6/1/2021
    identifier otherAJRUA6.0001121.pdf
    identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4270686
    description abstractIn France, a deep geological repository project is under development for radioactive waste management. The lack of knowledge from similar facilities and the large time scales involved result in uncertainties about the repository environment in operating conditions. The reliability methods are dedicated to dealing with such problematics and are used in this work to study the behavior of the overpack containing high-level radioactive waste. Its function is to isolate the waste from the environment for the first 500  years. The analysis is based on a finite-element model of the system integrating the time-related degradation of the system and considers a ductile fracture criterion. The stochastic structural model includes uncertain and time dependent corrosion rates and mechanical loading. A Kriging metamodel is calibrated in order to predict the behavior of the finite-element model with a much smaller computation time. The failure probability of the system is estimated using Monte Carlo simulations based on the results of both the finite-element model and the Kriging metamodel. The behavior of the system and the parameters having a first order influence on its performances are investigated through a sensitivity analysis.
    publisherASCE
    titleReliability Analysis of the Ductile Fracture of Overpacks for High-Level Radioactive Waste in Repository Conditions
    typeJournal Paper
    journal volume7
    journal issue2
    journal titleASCE-ASME Journal of Risk and Uncertainty in Engineering Systems, Part A: Civil Engineering
    identifier doi10.1061/AJRUA6.0001121
    journal fristpage04021010-1
    journal lastpage04021010-14
    page14
    treeASCE-ASME Journal of Risk and Uncertainty in Engineering Systems, Part A: Civil Engineering:;2021:;Volume ( 007 ):;issue: 002
    contenttypeFulltext
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