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Assessment of life of inner vessel for a pool-type fast breeder reactor based on inelastic and viscoplastic deformations
R. S. Alwar, Perumal Chellapandi
Published in
1993
Volume: 115
   
Issue: 2
Pages: 185 - 192
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 viscoplastic 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. © 1993 by ASME.
About the journal
JournalJournal of Pressure Vessel Technology, Transactions of the ASME
ISSN00949930
Open AccessNo
Concepts (24)
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    Creep
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    FAST-BREEDER
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    Life prediction
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    Nuclear reactors
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    Breeder reactors
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    Computational methods
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    Deformation
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    ELASTICITY
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    Fatigue of materials
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    Hardening
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    Mathematical models
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    Service life
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    Stainless steel
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    Stresses
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    Viscoplasticity
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    CHABOCHE VISCOPLASTIC MODEL
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    CREEP FATIGUE DAMAGE
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    INELASTICITY
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    KINEMATIC HARDENING MODEL
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    ORNL MATERIAL MODEL
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    POOL TYPE FAST BREEDER REACTORS
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    Ratcheting
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    STAINLESS STEEL TYPE 316 LN
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    Pressure vessels