Ketan Ajay
Materials Science · Purdue University West Lafayette
Publications
24
Citations
126
Est. group size
~1
Recurring co-author estimate
Active years
37
Publishing since 1989
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.
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
- Numerical Investigation into the Temperature Profile of a PHWR Channel Containing a Disassembled Fuel Bundle During a Postulated Accident Condition
Nuclear Technology · 2023
- Experimental and numerical study on the PHWR channel heat-up under an oxidizing environment
Nuclear Engineering and Design · 2022
- Numerical modeling of the thermal behavior of a severely damaged core of PHWR under accident condition
International Communications in Heat and Mass Transfer · 2022
- Understanding the influence of eccentric pressure tube on the thermal behavior of 37-element based PHWR channel under accident condition
Annals of Nuclear Energy · 2022
- Experimental study on thermo-chemical behavior of PHWR fuel channel under slumped fuel pin condition
Annals of Nuclear Energy · 2021
- Experimental and Numerical Investigation into Temperature Distribution of a Simulated PHWR Coolant Channel Under Heatup Condition
Nuclear Science and Engineering · 2021
- Thermal Behavior of a Completely Voided Coolant Channel for Indian PHWR Under Slumped Fuel Pin Condition: Experimental and Numerical Approach
Lecture notes in mechanical engineering · 2021
- ASSESSMENT OF HEAT TRANSFER IN FUEL CHANNEL OF INDIAN PHWR UNDER POSTULATED LARGE BREAK LOSS OF COOLANT ACCIDENT: EXPERIMENTAL AND NUMERICAL STUDY
EPJ Web of Conferences · 2021
- Influence of PT-CT contact on PHWR fuel channel thermal behaviour under accident condition – An experimental study
Nuclear Engineering and Design · 2020
- Experimental simulation of channel heat-up behaviour under slumped fuel pin condition for Indian PHWR
Annals of Nuclear Energy · 2020
- Radiative heat transfer analysis of 37-pin fuel bundle of Indian pressurized heavy water reactor under heat-up condition: experimental, numerical and analytical study
Energy Sources Part A Recovery Utilization and Environmental Effects · 2020
- Experimental investigation of radiation heat transfer in coolant channel under impaired cooling scenario for Indian PHWR
Nuclear Engineering and Design · 2019
- Thermal analysis of single channel for pressurized heavy water reactor during LOCA- A numerical approach
Proceeding of Proceedings of the 25th National and 3rd International ISHMT-ASTFE Heat and Mass Transfer Conference (IHMTC-2019) · 2019
- VARIATION OF TOTAL EMISSIVITY OF FUEL PIN OF IPHWR WITH TEMPERATURE
Proceeding of Proceedings of the 24th National and 2nd International ISHMT-ASTFE Heat and Mass Transfer Conference (IHMTC-2017) · 2018
- Combined Experimental and CFD Investigation of the Parabolic Shaped Solar Collector Utilizing Nanofluid (CuO-H<sub>2</sub>O and SiO<sub>2</sub>-H<sub>2</sub>O) as a Working Fluid
Journal of Engineering · 2016
- Nuclear Engineering and Design×4
- Annals of Nuclear Energy×3
- Nuclear Science and Engineering×2
- Nuclear Technology×2
- Journal of Engineering×1
- Wenzhong Zhou
Materials Science · Purdue University West Lafayette
- Logan Joyce
Materials Science · Purdue University West Lafayette
- Marat Khafizov
Materials Science · The Ohio State University
- Brandon Miller
Materials Science · Purdue University West Lafayette
- Md Ali Muntaha
Materials Science · Purdue University West Lafayette
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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