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 | 102 | 2017 |
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 | 23 | 2018 |
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 | 22 | 2013 |
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 | 16 | 2013 |
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 | 14 | 2018 |
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 | 12 | 2016 |
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 | 10 | 2015 |
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 | 9 | 2017 |
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 | 8 | 2015 |
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 | 7 | 2014 |
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 | 4 | 2011 |
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 | 3 | 2017 |
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 | 3 | 2010 |
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 | 2 | 2019 |
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 | 1 | 2018 |
Blind Calculation Results for SP-3 and SP-2 M Kumar, RK Bagul, PK Vijayan | 1 | 2012 |
Blind Calculation Results for SP-3 and SP-2 M Kumar, RK Bagul, PK Vijayan | 1 | 2012 |
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 | 1 | 2009 |
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 |