Current Projects

Design and Development of Robust and Effective Battery Thermal Management Systems (BTMS) for Electric Vehicles (EVs)

Sponsor: CRG, ANRF (formerly SERB), Govt. of India | Amount: Rs. 63.36 lakhs

Investigators: Dr. Mohd. Kaleem Khan (PI)| Dr. Manabendra Pathak (co-PI) | Duration: May 2024 - May 2027

Summary

This project focuses on creating an efficient and robust thermal management system for Li-ion batteries in electric vehicles. Since batteries generate significant heat, effective cooling is crucial to prevent thermal runaway and ensure optimal performance between 20-50°C. The research aims to design, fabricate, and test an advanced battery thermal management system that overcomes the limitations of current air and indirect liquid cooling methods, especially in challenging conditions like high ambient temperatures or heavy traffic.

Related Publications
  • Piyusha Jha, M. Hussain, M.K. Khan, 2024, Numerical evaluation of nanofluid-based indirect liquid cooling of a Li-ion battery pack... International Communications in Heat and Mass Transfer, Vol. 159, p.108079.
  • M. Hussain, M.K. Khan, and M. Pathak, 2024, Thermal management of high-energy lithium titanate oxide batteries using an effective channeled dielectric fluid immersion cooling system, Energy Conversion and Management, Vol. 313, p.118644.
  • M. Hussain, M.K. Khan, and M. Pathak, 2023, Thermal Analysis of Phase change material encapsulated Li-ion battery pack using multi-scale multi-dimensional framework, Journal of Energy Storage, Vol. 65, p.107290.

Completed Projects

Porous membrane based vapour venting technique for performance improvement in microchannel heat sink

Sponsor: CRG, ANRF (formerly SERB), Govt. of India | Amount: Rs. 32.83 lakhs

Investigators: Dr. Manabendra Pathak (PI) | Dr. Mohd. Kaleem Khan (co-PI)| Duration: November 2021 - March 2025

Summary

Flow boiling in microchannels is a highly effective method for cooling high-power-density electronics but suffers from instabilities caused by explosive vapor growth. This project introduced a novel nanoporous membrane-based vapor venting technique to mitigate these instabilities. By using a hydrophobic membrane to selectively remove vapor, the system prevents the formation of an upstream compressible volume, thereby enhancing heat transfer rates and increasing the critical heat flux limit.

Related Publications
  • A. Priy, M.D. Eqbal, M.Pathak, and M.K. Khan, 2025, Suppression of flow boiling instabilities in microchannel heat sinks using a passive vapor venting technique, Thermal Science and Engineering Progress, Vol. 65, p.103909.
  • A. Priy, I. Ahmad, A. Ranjan, M.Pathak, and M.K. Khan, 2024, Flow boiling characteristics in a microchannel heat sink with a condensing cover plate, Thermal Science and Engineering Progress, Vol. 53, p.102707.
  • A. Priy, S. Raj, M.Pathak, and M.K. Khan, 2022, A hydrophobic porous substrate-based vapor venting technique for mitigating flow boiling instabilities in microchannel heat sink, Applied Thermal Engineering, vol. 216, p.119138.

Effect of burnup on ballooning and burst behavior of Zircaloy-4 cladding tubes under simulated LOCA

Sponsor: Board of Research in Nuclear Sciences, DAE, Govt. of India | Amount: Rs. 32.991 lakhs

Investigators: Dr. Mohd. Kaleem Khan (PI)| Dr. Manabendra Pathak (co-PI) | Duration: November 2019 - May 2025

Summary

This research investigated the failure behavior of Zircaloy-4 nuclear fuel pins under simulated Loss-of-Coolant-Accident (LOCA) conditions. The study focused on how pre-oxidation (simulating high burnup) affects the cladding's microstructure and mechanical response, including creep, rupture, and embrittlement. By conducting burst tests in a steam environment, the project developed a burst criterion model that improves the understanding of fuel clad safety for Indian PHWRs.

Related Publications
  • S.Sagar, M.K. Khan, M. Pathak, et al., 2024, Zircaloy-4 fuel pin failure under simulated loss-of-coolant-accident conditions: Creep and rupture, Nuclear Engineering and Design, Vol. 428, p.113507.
  • S.Sagar, M.K. Khan, M. Pathak, et al., 2024, Zircaloy-4 fuel pin failure under simulated loss-of-coolant-accident conditions: Oxygen embrittlement, Progress in Nuclear Energy, Vol. 177, p.105485.

A self-adaptive electronic cooling system by enhanced pool boiling

Sponsor: CRG, ANRF (formerly SERB), Govt. of India | Amount: Rs. 36 lakhs

Investigators: Dr. Manabendra Pathak (PI) | Dr. Mohd. Kaleem Khan (co-PI)| Duration: May 2016 - March 2021

Summary

The project mainly focuses on the development of a self-adaptive cooling system based on a closed-loop two-phase thermosyphon (CLTPT) with enhanced heat transfer in the evaporator and the condenser. The first part of the report explains heat transfer enhancement with structured surfaces, and the second part presents the temperature-controlled self-adaptive thermosyphon loop. A closed-loop two-phase thermosyphon (CLTPT) is a gravity-assisted heat dissipation device that works on the principle of evaporation and condensation to facilitate large amounts of heat transfer without any pumping device. An efficient heat transfer mechanism should act in the evaporator and the condenser to produce a sufficient buoyancy effect in the loop. In the first part of the work, an effort is being made to enhance the heat transfer in the evaporator section with a structured heating surface.

Related Publications
  • V. Kumar, M. Pathak, and M.K. Khan, 2021, Heat transfer characteristics of a closed-loop two phase thermosyphon system with a structured heating surface, ASME Journal of Thermal Science and Engineering Applications,vol. 14, 011013.

Influence of Hydrogen Content on Burst Characteristics of Zircaloy-4 Cladding

Sponsor: Board of Research in Nuclear Sciences, DAE, Govt. of India | Amount: Rs. 31.18 Lacs

Investigators: Dr. Mohd. Kaleem Khan (PI)| Dr. Manabendra Pathak (co-PI) | Duration: October 2014 - December 2017

Summary

This project aimed to determine the effects of hydrogen embrittlement on the mechanical properties of Zircaloy-4 fuel cladding. The research used experimental and numerical techniques to study how the presence of hydrides alters creep performance, crack behavior, and burst characteristics during normal operation and accident scenarios like LOCA. The findings are crucial for understanding the degradation and lifespan of cladding in water-cooled nuclear reactors.

Related Publications
  • S. Suman, M.K. Khan, M. Pathak and R.N. Singh, 2018, Effects of hydrogen on thermal creep behaviour of Zircaloy fuel cladding, Journal of Nuclear Materials, vol.498, pp.20-32.
  • S. Suman, M.K. Khan, M. Pathak and R.N. Singh, 2018, Effects of delta-hydride precipitated at a crack tip on crack instability in Zircaloy-4, International Journal of Energy Research, vol.42, pp. 284-292.
  • S. Suman, M.K. Khan, M. Pathak and R.N. Singh, 2017, Investigation of elevated-temperature mechanical properties of delta-hydride precipitate in zircaloy-4 fuel cladding tubes using nanoindentation, Journal of Alloys and Compounds, vol.726, pp. 107-113.
  • S. Suman, M.K. Khan, M. Pathak and R.N. Singh, 2017, 3D simulation of hydride-assisted crack propagation in zircaloy-4 using XFEM, International Journal of Hydrogen Energy, vol. 42, pp.18668-18673.
  • S. Suman, M.K. Khan, M. Pathak and R.N. Singh, 2016, Rupture behaviour of nuclear fuel cladding during loss-of-coolant accident, Nuclear Engineering and Design, vol. 307, pp. 319-327.
  • S.Suman, M.K. Khan, M.Pathak and R.N. Singh, J.K. Chakravartty, 2015, Hydrogen in Zircaloy: Mechanism and its Impacts, International Journal of Hydrogen Energy, Vol.40(17), pp.5976-5994.

Evaluation of Burst Criterion of Zircaloy Clad

Sponsor: Atomic Energy Regulatory Board, DAE, Govt. of India | Amount: Rs. 25.445 Lacs

Investigators: Dr. Mohd. Kaleem Khan (PI) | Duration: January 2010 - May 2013

Summary

The research work was undertaken with an objective to develop the burst criterion for zircaloy- clad tubes used in Indian pressurized heavy water reactors (PHWRs) in an outside inert environment. To serve this objective, an indigenous experimental clad burst facility was developed at IIT Patna. The clad specimens were heated at different heating rates (17 to 81 K/s) and at different internal overpressures (20, 40, 60 and 80 bar) until they burst. A total of 36 tubes were tested for burst for different combinations of heating rate and internal overpressure. The temperature, pressure and wall displacement were measured online. The offline measurements were also conducted on the burst specimen to determine the burst parameters like circumference and thickness at the burst location. These parameters were then used to determine the burst stress and burst strains.The results of the burst criterion have been validated with the present and past data. It is worth mentioning that the proposed burst criterion model has also taken into account the effect of pressure rise during the heating of clad specimen. It has been found that the inclusion of rate of pressure-rise has a remarkable effect on the predicted burst parameters and has resulted in a better agreement with the experimental data.

Related Publications
  • M.K. Khan and M. Pathak, 2014, Ballooning deformation of Zircaloy-4 fuel sheath, ASME Journal of Pressure Vessel Technology, vol. 136, pp. 031206
  • M.K. Khan, M. Pathak, S. Suman, A. Deo, A., and R. Singh, 2014, Burst Investigation on Zircaloy-4 Claddings in Inert Environment, Annals of Nuclear Energy, vol. 69, pp.292-300.
  • M.K. Khan, M. Pathak, A. Deo, A., and R. Singh, 2013, Burst Criterion for zircaloy-4 cladding in an inert environment, Nuclear Engineering and Design, vol. 265, pp. 886-894.
  • T. Alam, M.K. Khan, M. Pathak, K. Ravi, R. Singh,and S.K. Gupta, 2011. A Review on the Clad Failure Studies, Nuclear Engineering and Design, vol. 241(9), pp. 3658-3677.