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Ketan Ajay

Materials Science · Purdue University West Lafayette

Established · publishing since 1989

Publications

24

Citations

126

Est. group size

~1

Recurring co-author estimate

Active years

37

Publishing since 1989

Research summary
AI-generated

Ketan Ajay's research focuses on the thermal and heat-transfer behavior of Pressurized Heavy Water Reactor (PHWR) fuel channels under accident conditions, such as loss-of-coolant scenarios and fuel bundle damage. The work combines experimental testing with numerical simulations (CFD) to understand how reactor components heat up, deform, and transfer heat under abnormal operating conditions. This research is relevant to nuclear reactor safety analysis, particularly for reactor designs used in the Indian nuclear power program.

Nuclear reactor safety and accident analysisPHWR fuel channel thermal behaviorHeat transfer and radiative heat transfer modelingComputational fluid dynamics (CFD) simulationNuclear engineering thermal-hydraulics

Publication output has grown from essentially none in 2017 to a steady average of about 2 papers per year over the last five years, with some year-to-year fluctuation but no clear slowdown.

Generated by claude-sonnet-5 from public bibliographic data · Jul 20, 2026

Publication cadence
Publications per year over the last 10 years — averaging 2.0/year recently
172018: 1 publication182019: 2 publications192020: 3 publications202021: 4 publications4212022: 3 publications222023: 1 publication232024: 4 publications4242025: 2 publications2526
Recent publications
Publishes in
  • Nuclear Engineering and Design×4
  • Annals of Nuclear Energy×3
  • Nuclear Science and Engineering×2
  • Nuclear Technology×2
  • Journal of Engineering×1
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This profile was generated automatically from public scholarly data (OpenAlex). Group size and activity levels are estimates derived from co-authorship patterns.

Last updated Jul 20, 2026.

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