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Dynamic Strain Aging in New Generation Cr-Mo-V Steel for Reactor Pressure Vessel Applications

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Abstract

A new generation nuclear reactor pressure vessel steel (CrMoV type) having compositional similarities with thick section 3Cr-Mo class of low alloy steels and adapted for nuclear applications was investigated for various manifestations of dynamic strain aging (DSA) using uniaxial tests. The steel investigated herein has undergone quenched and tempered treatment such that a tempered bainite microstructure with Cr-rich carbides was formed. The scope of the uniaxial experiments included tensile tests over a temperature range of 298 K to 873 K (25 °C to 600 °C) at two strain rates (10−3 and 10−4 s−1), as well as suitably designed transient strain rate change tests. The flow behavior displayed serrated flow, negative strain rate sensitivity, plateau behavior of yield, negative temperature (T), and strain rate \( \left( {\dot{\varepsilon }} \right) \) dependence of flow stress over the temperature range of 523 K to 673 K (250 °C to 400 °C) and strain rate range of 5 × 10−3 s−1 to 3 × 10−6 s−1, respectively. While these trends attested to the presence of DSA, a lack of work hardening and near negligible impairment of ductility point to the fact that manifestations of embrittling features of DSA were significantly enervated in the new generation pressure vessel steel. In order to provide a mechanistic understanding of these unique combinations of manifestations of DSA in the steel, a new approach for evaluation of responsible solutes from strain rate change tests was adopted. From these experiments and calculation of activation energy by application of vacancy-based models, the solutes responsible for DSA were identified as carbon/nitrogen. The lack of embrittling features of DSA in the steel was rationalized as being due to the beneficial effects arising from the presence of dynamic recovery effects, presence of alloy carbides in the tempered bainitic structure, and formation of solute clusters, all of which hinder the possibilities for strong aging of dislocations.

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  1. PHILIPS is a trademark of FEI Company, Hillsboro, OR.

  2. INSTRON is a trademark of Canton, Norwood, MA.

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Acknowledgments

One of the authors (CG) acknowledges the support of Professor Dr. Ing. i.R. W. Blum, Institute fur Werkstoffwissenscaften, Universitat Erlangen–Nurenberg, during the Indo German (INDO-FRG) collaboration program for the preparation and study of the extraction replica of the steel under investigation.

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Authors and Affiliations

  1. Mechanical Metallurgy Section, Materials Group, Bhabha Atomic Research Centre, Trombay, Mumbai, 400085, India

    C. Gupta (Scientific Officer) & J. K. Chakravartty (Head)

  2. Department of Atomic Energy, Government of India, CSM Marg, Mumbai, 40001, India

    S. Banerjee (Chairman Atomic Energy Commission and Secretary to Government of India)

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  1. C. Gupta
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  3. S. Banerjee
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Correspondence to C. Gupta.

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Manuscript submitted August 9, 2009.

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Gupta, C., Chakravartty, J.K. & Banerjee, S. Dynamic Strain Aging in New Generation Cr-Mo-V Steel for Reactor Pressure Vessel Applications. Metall Mater Trans A 41, 3326–3339 (2010). https://doi.org/10.1007/s11661-010-0409-x

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