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Potentiality of Small Punch Test Using Damage Model to Generate J-R Curve of 20MnMoNi55

  • Pradeep KumarEmail author
  • B. K. Dutta
  • J. Chattopadhyay
  • R. S. Shriwastaw
Conference paper
  • 889 Downloads
Part of the Lecture Notes in Mechanical Engineering book series (LNME)

Abstract

This study explored the determination of J-R curve and J i (fracture toughness) of nuclear structural materials using small punch test of 3 mm disk. The punch load versus central deflection data are collected up to fracture which is signified by the rapid drop in load carrying capability of the specimens. The experimental data for 20MnMoNi55 material is then used to evaluate yield strength and ultimate tensile strength making use of available correlations in the previous studies. These material data are then used to calculate Ramberg–Osgood hardening exponent leading to the generation of complete true stress–strain data. The next task is to determine GTN parameters of the materials which can simulate average \( P/t_{0}^{2} \) versus biaxial strain up to fracture. These GTN parameters along with true stress–strain data are then used to generate J-R curves of the materials by finite element modeling of ASTM standard CT specimen. Calculated J-R curves are then compared with the experimental values of previous studies. The proposed methodology has the potential to determine J-R curve and J i (fracture toughness) of irradiated material using small punch test.

Keywords

Miniaturized SPT specimens Finite element analysis Gurson model J-R curve Biaxial strain 

References

  1. 1.
    Mao X, Takahashi H (1987) Development of a further miniaturized specimen of 3 mm diameter for TEM disk (φ 3 mm) small punch tests. J Nucl Mater 150:42–52CrossRefGoogle Scholar
  2. 2.
    Mao X, Takahashi H, Kodaira T (1992) Supersmall punch test to estimate fracture toughness Jic and its application to radiation embrittlement of 2.25 Cr–1Mo steel. Mater Sci Eng A150:231–236CrossRefGoogle Scholar
  3. 3.
    Misawa T, Nagata S et al (1989) Fracture toughness evaluation of fusion reactor structural steels at low temperatures by small punch tests. J Nucl Mater 169:225–232CrossRefGoogle Scholar
  4. 4.
    Finarelli D, Roedig M, Carsughi F (2004) Small punch test on austenitic steel and martensitic steels irradiated in a spallation environment with 530 MeV protons. J Nucl Mater 328:146–150CrossRefGoogle Scholar
  5. 5.
    Guan Kaishu, Hua Li et al (2011) Assessment of toughness in long term service CrMo low alloy steel by fracture toughness and small punch test. Nucl Eng Des 241:1407–1413CrossRefGoogle Scholar
  6. 6.
    Rodríguez C, Cardenas E et al (2013) fracture characterization of steels by means of the small punch test. Exp Mech 53:385–392CrossRefGoogle Scholar
  7. 7.
    Alegre JM, Cuesta II, Bravo PM (2011) Implementation of the GTN damage model to simulate the small punch test on pre-cracked specimens. Procedia Eng 10:1007–1016CrossRefGoogle Scholar
  8. 8.
    Kumar P, Dutta BK, Chattopadhyay J, Shriwastaw RS (2016) Numerical evaluation of J-R curve using small punch test data. Theor Appl Fract Mechan (2016), dx.doi.org/ 10.1016/j.tafmec.2016.08.003
  9. 9.
    Garcia TE, Rodriguez C et al (2014) Estimation of the mechanical properties of metallic materials by means of the small punch test. J Alloy Comp 582:708–717CrossRefGoogle Scholar
  10. 10.
    El-Fadaly MS, El-Sarrage TA, Eleiche AM, Dahl W (1995) Fracture toughness of 20MnMoNi55 steel at different temperatures as affected by room-temperature pre-deformation. J Mater Process Technol 54:159–165CrossRefGoogle Scholar
  11. 11.
    Kumar P, Chattopadhyay J, Dutta BK (2016) On the correlation between minimum thickness and central deflection during small punch test. J Nucl Mater 475:37–45CrossRefGoogle Scholar
  12. 12.
    In house finite element code MADAM (MAterial DAmage Modeling) developed by Reactor Safety Division (RSD), BARC technical report (1999), IndiaGoogle Scholar
  13. 13.
    Dutta BK, Guin S, Sahu MK, Samal MK (2008) A phenomenological form of the q2 parameter in the Gurson model. Int J Press Vessels Pip 85:199–210CrossRefGoogle Scholar

Copyright information

© Springer Nature Singapore Pte Ltd. 2018

Authors and Affiliations

  • Pradeep Kumar
    • 1
    Email author
  • B. K. Dutta
    • 1
  • J. Chattopadhyay
    • 1
    • 2
  • R. S. Shriwastaw
    • 3
  1. 1.Homi Bhabha National InstituteMumbaiIndia
  2. 2.Reactor Safety DivisionBhabha Atomic Research CentreMumbaiIndia
  3. 3.Post Irradiation Examination DivisionBhabha Atomic Research CentreMumbaiIndia

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