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Mukesh Dhiman
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CFD simulations of a bubble column with and without internals by using OpenFOAM
VH Bhusare, MK Dhiman, DV Kalaga, S Roy, JB Joshi
Chemical Engineering Journal 317, 157-174, 2017
1022017
Mixing in a co‐current upflow bubble column reactors with and without internals
VH Bhusare, DV Kalaga, MK Dhiman, JB Joshi, S Roy
The Canadian Journal of Chemical Engineering 96 (9), 1957-1971, 2018
232018
Managing a prolonged station blackout condition in AHWR by passive means
M Kumar, AK Nayak, V Jain, PK Vijayan, KK Vaze
Nuclear Engineering and Technology 45 (5), 605-612, 2013
222013
Role of passive safety features in prevention and mitigation of severe plant conditions in indian advanced heavy water reactor
V Jain, AK Nayak, M Dhiman, PP Kulkarni, PK Vijayan, KK Vaze
Nuclear Engineering and Technology 45 (5), 625-636, 2013
162013
CFD simulation of boiling flows inside fuel rod bundle of a natural circulation BWR during SBO
M Kumar, A Moharana, AK Nayak, J J. B.
Nuclear Engineering and Design 338, 300-329, 2018
142018
Experimental and CFD simulations of fluid flow and temperature distribution in a natural circulation driven Passive Moderator Cooling System of an advanced nuclear reactor
E Pal, M Kumar, AK Nayak, JB Joshi
Chemical Engineering Science 155, 45-64, 2016
122016
Conceptual design of a passive moderator cooling system for a pressure tube type natural circulation boiling water cooled reactor
M Kumar, E Pal, AK Nayak, PK Vijayan
Nuclear Engineering and Design 291, 261-270, 2015
102015
Investigations of natural convection and circulation in Passive Moderator Cooling System of an advanced reactor in a scaled test facility
M Kumar, AK Nayak, JB Joshi
Nuclear Engineering and Design 322, 55-67, 2017
92017
CFD simulations of moderator flow inside Calandria of the Passive Moderator Cooling System of an advanced reactor
E Pal, M Kumar, JB Joshi, AK Nayak, PK Vijayan
Nuclear Engineering and Design 292, 193-203, 2015
82015
Reliability assessment of passive containment cooling system of an advanced reactor using APSRA methodology
M Kumar, A Chakravarty, AK Nayak, H Prasad, V Gopika
Nuclear Engineering and Design 278, 17-28, 2014
72014
Simulation of natural circulation in a rectangular loop using CFD code PHOENICS
M Kumar, A Borghain, NK Maheshwari, PK Vijayan
Kerntechnik 76 (2), 93-97, 2011
42011
Experimental demonstration of AHWR safety during prolonged station black out
M Kumar, PK Verma, AK Nayak, A Rama Rao
Journal of Nuclear Engineering and Radiation Science 3 (4), 041012, 2017
32017
Scaling philosophy and system description of AHWR thermal-hydraulic test facility (ATTF)
M Kumar, A Dasgupta, AK Vishnoi, V Jain, N Kumar, K Bodkha, ...
Bhabha Atomic Research Centre, 2010
32010
Experimental Demonstration of Decay Heat Removal by Submerged Feeders in a Full-Scale Test Facility of a Natural Circulation Boiling Water Reactor
AK Nayak, M Kumar, SV Prasad, V Jain, DK Chandraker
Journal of Nuclear Engineering and Radiation Science 5 (4), 041203, 2019
22019
Experimental Demonstration of Safety of AHWR during Stagnation Channel Break Condition in an Integral Test Loop
M Kumar, AK Nayak, SV Prasad, PK Verma, RK Singh, V Jain, ...
Journal of Nuclear Engineering and Radiation Science 4 (2), 021005, 2018
12018
Blind Calculation Results for SP-3 and SP-2
M Kumar, RK Bagul, PK Vijayan
12012
Blind Calculation Results for SP-3 and SP-2
M Kumar, RK Bagul, PK Vijayan
12012
An experimental study on the thermal-hydraulics characteristics of a boiling two-phase natural circulation loop with Al2O3 nanofluids
AK Nayak, PP Kulkarni, MK Dhiman
12009
Safety analysis of AHWR for post-Fukushima type scenario
M Kumar, PP Kulkarni, MT Kamble, AK Nayak, PK Vijayan, KK Vaze
Proceedings of the international workshop on new horizons in nuclear reactor …, 2014
2014
Comparison of RELAP5 and CATHARE predictions in Simulation of Natural Circulation in a Test Facility
M Kumar, RK Bagul, AK Nayak, PK Vijayan, D Saha
2011
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