• Numerical simulation with finite element and artificial neural network of ball indentation for mechanical property estimation

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      Permanent link:
      https://www.ias.ac.in/article/fulltext/sadh/036/02/0181-0192

    • Keywords

       

      Automated ball indentation; ANN; finite element simulation; irradiated nuclear material; miniature specimen testing.

    • Abstract

       

      A combined mechanical property evaluation methodology with ABI (Automated Ball Indentation) simulation and Artificial Neural Network (ANN) analysis is evolved to evaluate the mechanical properties for Carbon Manganese Steel (SA-333 Grade-6) and Stainless Steel (SS-304LN). The experimental load deflection data is converted into meaningful mechanical properties for these materials and their evaluated property is verified with experimental tensile specimen results. An ANN database is generated with the help of contact type finite element analysis by numerically simulating the ABI process for various magnitudes of yield strength $(\sigma_{yp})$ (200 MPa–400 MPa) with a range of strain hardening exponent (n) (0.05–0.5)$and strength coefficient (K) (600 MPa–1600 MPa). For the present problem, a ball indenter of 1.57 mm diameter having Young’s modulus higher than test piece is used to minimize the error due to indenter deformation. Test piece dimension is kept large enough in comparison to the indenter configuration in the simulation to minimize the deflection at the outer edge of the test piece. Further, this database after the neural network training; is used to analyse measured material properties of different test pieces. The ANN predictions are reconfirmed with contact type finite element analysis for an arbitrary selected test sample. The methodology evolved in this work can be extended to predict material properties for any irradiated nuclear material in the service. Extensions of the ABI tests and the associated database analysis could lead to evaluation of the indentation energy to fracture needed for the structural integrity assessment of aged components.

    • Author Affiliations

       

      Kamal Sharma1 Vivek Bhasin1 K K Vaze1 A K ghosh1

      1. Reactor Safety Division, Bhabha Atomic Research Centre (BARC), Trombay, Mumbai 400 085, India
    • Dates

       

© 2017-2019 Indian Academy of Sciences, Bengaluru.