G. Padmakumar

Indira Gandhi Centre for Atomic Research — India

Engineering · Physical Sciences

14h-index637citations59works0.02yr avg
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Research Topics

Nuclear Engineering Thermal-Hydraulics(30), Nuclear reactor physics and engineering(22), Nuclear Materials and Properties(13), Flow Measurement and Analysis(8), Metallurgy and Material Forming(5)

Publications59 total

Computational fluid dynamic investigations on effects of inserts in fast reactor fuel bundle hydraulics
Progress in Nuclear Energy·2019· 1 cited
Thermal-hydraulic effects of inserts in a fast reactor fuel bundle
Nuclear Engineering and Design·2018· 2 cited
COMPUTATIONAL FLUID DYNAMIC INVESTIGATIONS ON EFFECTS OF CIRCULAR ROD INSERTS IN FAST REACTOR FUEL BUNDLE
Proceeding of Proceedings of the 24th National and 2nd International ISHMT-ASTFE Heat and Mass Transfer Conference (IHMTC-2017)·2018
Design, development and experiential validation of large stroke welded disk bellows for nuclear industry
International Journal of Design Engineering·2018
Testing in sodium and qualification of the bearings used in inclined fuel transfer machine of prototype fast breeder reactor
International Journal of Nuclear Energy Science and Technology·2018Open Access
Design, development and experiential validation of large stroke welded disk bellows for nuclear industry
International Journal of Design Engineering·2018
Testing in sodium and qualification of the bearings used in inclined fuel transfer machine of prototype fast breeder reactor
International Journal of Nuclear Energy Science and Technology·2018
Performance evaluation of decay heat removal system of PFBR with partial availability of air side dampers
Nuclear Engineering and Design·2017· 8 cited
Experience of various materials for design and manufacture of bellows for nuclear industry
Advanced Materials Proceedings·2017· 15 citedOpen Access
Manufacturing experiences of large stroke welded disc bellows for nuclear applications
2017· 2 cited
Hydraulic characteristics of a fast reactor fuel subassembly: An experimental investigation
Annals of Nuclear Energy·2017· 14 cited
Evaluation of hydraulic characteristics of core flow monitoring mechanism for PFBR
Annals of Nuclear Energy·2016· 1 cited
Numerical Simulation and Experimental Validation of Future FBR Surge Tank Hydraulics
Lecture notes in mechanical engineering·2016
Design and performance evaluation of Core Flow Monitoring Mechanisms for PFBR
Annals of Nuclear Energy·2016· 2 cited
Design and Analysis of Bellows for High Temperature Application as Per RCC-MR
Transactions of the Indian Institute of Metals·2016· 8 cited
Optimisation of thermal baffle for liquid metal injection nozzle
International Journal of Nuclear Energy Science and Technology·2016
Optimisation of thermal baffle for liquid metal injection nozzle
International Journal of Nuclear Energy Science and Technology·2016
Process optimisation of a liquid sodium economiser circuit
Progress in Nuclear Energy·2015
A methodology to determine thermal conductivity of soils from flux measurement
Geomechanics and Geoengineering·2015· 24 cited
Experimental study on the transient response of passive decay heat removal system
Nuclear Engineering and Design·2014· 7 cited
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Frequent Co-authors

K.K. Rajan(18), G. Vaidyanathan(15), Indranil Banerjee(10), G.K. Pandey(9), V. Vinod(8), Ashwin W. Patwardhan(7), V. Prakash(7), B.K. Sreedhar(5), S. C. S. P. Kumar Krovvidi(5), K. Velusamy(5), D. Ramdasu(4), P. Kalyanasundaram(4), B.K. Nashine(4), S. Chandramouli(4), C. Meikandamurthy(4), B. V. S. S. S. Prasad(4), P. Selvaraj(4), Devendra Narain Singh(3), M. Thirumalai(3), C. Anandbabu(3)