Mr
Indira Gandhi Centre for Atomic Research
Author in the following contributions
- Thermal Hydraulic Simulation of Loss of Flow Without Scram Test in FFTF using DYANA-P code
- DEVELOPMENT OF COOLANT VOIDING MODEL FOR FAST REACTOR CORE
- Computational fluid dynamics study for estimation of dilution for failed fuel location system
- Integrated thermal hydraulic analysis of Hot and Cold Pools of a liquid sodium cooled 600 MWe fast reactor
