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Anil Kumar Sharma
Anil Kumar Sharma
Professor, Department of Mechanical Engineering, Jamia Millia Islamia ( A Central University ), New
在 jmi.ac.in 的电子邮件经过验证
标题
引用次数
引用次数
年份
Conjugate turbulent natural convection with surface radiation in air filled rectangular enclosures
AK Sharma, K Velusamy, C Balaji, SP Venkateshan
International Journal of Heat and Mass Transfer 50 (3-4), 625-639, 2007
1412007
Interaction effects between laminar natural convection and surface radiation in tilted square and shallow enclosures
V Vivek, AK Sharma, C Balaji
International Journal of Thermal Sciences 60, 70-84, 2012
1002012
A review of sub-channel thermal hydraulic codes for nuclear reactor core and future directions
A Moorthi, AK Sharma, K Velusamy
Nuclear Engineering and Design 332, 329-344, 2018
922018
Turbulent natural convection in an enclosure with localized heating from below
AK Sharma, K Velusamy, C Balaji
International Journal of Thermal Sciences 46 (12), 1232-1241, 2007
862007
Interaction of turbulent natural convection and surface thermal radiation in inclined square enclosures
AK Sharma, K Velusamy, C Balaji
Heat and mass transfer 44, 1153-1170, 2008
422008
Turbulent natural convection of sodium in a cylindrical enclosure with multiple internal heat sources: A conjugate heat transfer study
AK Sharma, K Velusamy, C Balaji
International Journal of Heat and Mass Transfer 52 (11-12), 2858-2870, 2009
402009
PATH–An experimental facility for natural circulation heat transfer studies related to Post Accident Thermal Hydraulics
L Gnanadhas, AK Sharma, B Malarvizhi, SS Murthy, EH Rao, ...
Nuclear Engineering and Design 241 (9), 3839-3850, 2011
302011
Conjugate transient natural convection in a cylindrical enclosure with internal volumetric heat generation
AK Sharma, K Velusamy, C Balaji
Annals of Nuclear Energy 35 (8), 1502-1514, 2008
292008
Investigation of fragmentation phenomena and debris bed formation during core meltdown accident in SFR using simulated experiments
AM Mathai, AK Sharma, J Anandan, B Malarvizhi, SK Das, BK Nashine, ...
Nuclear Engineering and Design 292, 87-97, 2015
272015
Conjugate laminar natural convection and surface radiation in enclosures: Effects of protrusion shape and position
S Patil, AK Sharma, K Velusamy
International Communications in Heat and Mass Transfer 76, 139-146, 2016
212016
Integrated CFD investigation of heat transfer enhancement using multi-tray core catcher in SFR
AK Sharma, K Velusamy
Annals of Nuclear Energy 104, 256-266, 2017
152017
A CFD based approach for thermal hydraulic design of main vessel cooling system of pool type fast reactors
V Vivek, AK Sharma, C Balaji
Annals of Nuclear Energy 57, 269-279, 2013
152013
Experimental study on thermo-chemical phenomena during interaction of limestone concrete with liquid sodium under inert atmosphere
SK Das, AK Sharma, FC Parida, N Kasinathan
Construction and Building Materials 23 (11), 3375-3381, 2009
142009
Design of core catchers for sodium cooled FBRs–Challenges
V Jhade, PK Shukla, AJ Sudha, AK Sharma, EH Rao, SK Das, G Lydia, ...
Nuclear Engineering and Design 359, 110473, 2020
122020
Melting and multi-phase flow modelling of nuclear fuel in fast reactor fuel rod
A Dubey, AK Sharma
International Journal of Thermal Sciences 125, 256-272, 2018
122018
Thermal hydraulic parametric investigation of decay heat removal from degraded core of a sodium cooled fast Breeder reactor
L Verma, AK Sharma, K Velusamy
Nuclear Engineering and Design 313, 285-295, 2017
112017
Interaction of natural convection flow in multiple open cavities formed due to horizontal fins
AK Sharma, A Pradeep, K Velusamy, P Chellapandi, B Raj
Annals of Nuclear Energy 38 (9), 1906-1915, 2011
72011
Sodium exposure tests on limestone concrete used as sacrificial protection layer in FBR
FC Parida, SK Das, AK Sharma, PM Rao, SS Ramesh, PA Somayajulu, ...
International Conference on Nuclear Engineering 42460, 309-318, 2006
72006
Enhancement in heat transfer from heat generating core debris using a passive approach in fast reactors: 3-D CFD analysis
V Jhade, AK Sharma
International Journal of Thermal Sciences 160, 106636, 2021
62021
Semiempirical model for wet scrubbing of bubble rising in liquid pool of sodium-cooled fast reactor
A Pradeep, AK Sharma
Nuclear Engineering and Technology 50 (6), 849-853, 2018
62018
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