S. V. Prasad

Critical Heat Flux on Curved Calandria Vessel of Indian PHWRs During Severe Accident Condition

A. K. Nayak, P. P. Kulkarni, P. Verma, 2021 .

Experimental Evaluation of Critical Heat Flux in Downward-Facing Boiling on SS304 L Flat Plate Relevant to In-Calandria Retention in PHWRs

A. Nayak, S. V. Prasad, 2020 .

Modelling of core melt scenarios in nuclear reactors

P. P. Kulkarni, A. Nayak, S. V. Prasad, 2019, Advances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment.

Retention of Molten Corium in Calandria Vessel of PHWR With Moderator Drain Pipe

P. P. Kulkarni, A. Nayak, S. V. Prasad, 2020 .