Yatindra Kumar

About

I have been working as a scientific officer in the Department of Atomic Energy since August 2013. My area of work includes tensile and creep deformation; fracture mechanics focused on creep crack growth (CCG) studies, creep damage assessment, and microstructural investigation. I have experience working on projects on high-temperature materials important to nuclear reactors (thermal and fast reactors) and coal-fired thermal power plant applications.

• Investigation of creep crack growth behaviour and its mechanism in Indian Prototype Fast Breeder Reactor (PFBR) structural material
o Modified 9Cr–1Mo (P91) weldment
o Boron-added modified 9Cr-1Mo steel weldment
o Type 316(N) weld
o Dissimilar Metal Weld (DMW) joint of P91-SS316LN
o Creep-creep crack growth rate correlation methodology

• Principal collaborator for the creep crack growth projects towards the development of high-temperature materials for coal-fired thermal power plants under the “Advanced Ultra-Supercritical (AUSC) Project.”
o Alloy 625 cast
o Alloy 617 base and weld materials (Tube), Alloy 617 forge
o 10Cr-Alloy 617 BMW weld joint
o SS304HCu base and weld material

• Investigation of creep properties of Zr-2.5Nb pressure tube material of Indian PHWR thermal reactor
o Heat-treated Zr-2.5Nb alloy
o Effect of hydrogen/hydride on creep
o Threshold creep behaviour
o Effect of cold work
o Effect of manufacturing route

• Structure-property correlations based on electron microscopy under creep and creep crack growth regime.

Employment

• Bhabha Atomic Research Centre Scientific Officer
  2021 - Present
• Indira Gandhi Centre for Atomic Research Scientific Officer
  2013 - 2021
• Bhabha Atomic Research Centre Trainee Scientific Officer
  2012 - 2013

Education

• Homi Bhabha National Institute PhD
  2019 - 2026
• Homi Bhabha National Institute M. Tech
  2012 - 2014
• Indian Institute of Engineering Science and Technology, Shibpur B. Tech
  2008 - 2012

Projects & Funding

Projects & funding information is unavailable.

Publications (10)

• A study on creep and creep crack growth correlation methodology in modified 9Cr-1Mo steel
  International Journal of Pressure Vessels and Piping 2026 0 citations DOI: 10.1016/j.ijpvp.2026.105848
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• Mitigation of hydride embrittlement in Zr-2.5 %Nb pressure tube material using palladium coating
  Journal of Nuclear Materials 2025 1 citation DOI: 10.1016/j.jnucmat.2025.156052
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• Insight into threshold creep behaviour in Zr-2.5Nb alloy
  Journal of Nuclear Materials 2025 1 citation DOI: 10.1016/j.jnucmat.2024.155599
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• A comparative study of creep crack growth behaviour amongst the dissimilar P91-IN182-SS316LN and similar P91 weld joints
  Materials at High Temperatures 2024 1 citation DOI: 10.1080/09603409.2024.2344898
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• Effect of annealing treatment on the creep behaviour of Zr-2.5Nb alloy
  Journal of Nuclear Materials 2024 4 citations DOI: 10.1016/j.jnucmat.2024.154949
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• Experimental investigation of creep crack growth behavior in the heat affected zone of boron added modified 9Cr–1Mo steel weld
  Materials Science and Engineering: A 2021 3 citations DOI: 10.1016/j.msea.2021.141180
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• Crystallographic slip transfer during creep crack growth in weldments of Fe-Cr-Ni-Mo (N) type steel
  DAE SOLID STATE PHYSICS SYMPOSIUM 2019 2020 0 citations DOI: 10.1063/5.0017400
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• Study of creep crack growth behaviour of a type 316(N) stainless steel weld and its mechanism
  Materials Science and Engineering: A 2018 17 citations DOI: 10.1016/j.msea.2018.06.096
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• Study of creep crack growth in a modified 9Cr–1Mo steel weld metal and heat affected zone
  Materials Science and Engineering: A 2016 31 citations DOI: 10.1016/j.msea.2015.12.053
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• Creep Crack Growth Behavior of a P91 Steel Weld
  Procedia Engineering 2014 10 citations DOI: 10.1016/j.proeng.2014.11.067
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