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    Assessment of Life of Inner Vessel for a Pool-Type Fast Breeder Reactor Based on Inelastic and Viscoplastic Deformations

    Source: Journal of Pressure Vessel Technology:;1993:;volume( 115 ):;issue: 002::page 185
    Author:
    R. S. Alwar
    ,
    P. Chellapandi
    ,
    S. B. Bhoje
    DOI: 10.1115/1.2929514
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Towards assessing the creep-fatigue damage for the inner vessel of a pool-type fast reactor, 3-D elastic and axisymmetric inelastic analysis with classical kinematic hardening model, ORNL material model and more realistic CHABOCHE visco-plastic model have been performed. The material properties of stainless steel type 316 LN at various temperatures are used in the analysis. Using the results of this analysis, the creep-fatigue damage and ratcheting are assessed as per the rules of RCC-MR and results have been compared for the various constitutive models used. Inelastic analysis has been performed only at highly stressed local regions. Computations with the ORNL material model is found to be satisfactory in terms of conservatism and computer cost involved, and hence recommended for use in the design stage. Further, conservatism in estimating the creep fatigue-damage of the component associated with the elastic route of RCC-MR has been quantified. The inelastic and viscoplastic analysis tool has been validated using experimental benchmark problems.
    keyword(s): Deformation , Vessels , Breeder reactors , Creep , Fatigue , Inelastic analysis , Computers , Computation , Fatigue damage , Stainless steel , Fast neutron reactors , Temperature , Hardening , Materials properties , Constitutive equations AND Design ,
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      Assessment of Life of Inner Vessel for a Pool-Type Fast Breeder Reactor Based on Inelastic and Viscoplastic Deformations

    URI
    https://yetl.yabesh.ir/yetl1/handle/yetl/112543
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    • Journal of Pressure Vessel Technology

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    contributor authorR. S. Alwar
    contributor authorP. Chellapandi
    contributor authorS. B. Bhoje
    date accessioned2017-05-08T23:42:23Z
    date available2017-05-08T23:42:23Z
    date copyrightMay, 1993
    date issued1993
    identifier issn0094-9930
    identifier otherJPVTAS-28345#185_1.pdf
    identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/112543
    description abstractTowards assessing the creep-fatigue damage for the inner vessel of a pool-type fast reactor, 3-D elastic and axisymmetric inelastic analysis with classical kinematic hardening model, ORNL material model and more realistic CHABOCHE visco-plastic model have been performed. The material properties of stainless steel type 316 LN at various temperatures are used in the analysis. Using the results of this analysis, the creep-fatigue damage and ratcheting are assessed as per the rules of RCC-MR and results have been compared for the various constitutive models used. Inelastic analysis has been performed only at highly stressed local regions. Computations with the ORNL material model is found to be satisfactory in terms of conservatism and computer cost involved, and hence recommended for use in the design stage. Further, conservatism in estimating the creep fatigue-damage of the component associated with the elastic route of RCC-MR has been quantified. The inelastic and viscoplastic analysis tool has been validated using experimental benchmark problems.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleAssessment of Life of Inner Vessel for a Pool-Type Fast Breeder Reactor Based on Inelastic and Viscoplastic Deformations
    typeJournal Paper
    journal volume115
    journal issue2
    journal titleJournal of Pressure Vessel Technology
    identifier doi10.1115/1.2929514
    journal fristpage185
    journal lastpage192
    identifier eissn1528-8978
    keywordsDeformation
    keywordsVessels
    keywordsBreeder reactors
    keywordsCreep
    keywordsFatigue
    keywordsInelastic analysis
    keywordsComputers
    keywordsComputation
    keywordsFatigue damage
    keywordsStainless steel
    keywordsFast neutron reactors
    keywordsTemperature
    keywordsHardening
    keywordsMaterials properties
    keywordsConstitutive equations AND Design
    treeJournal of Pressure Vessel Technology:;1993:;volume( 115 ):;issue: 002
    contenttypeFulltext
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