Indira Gandhi Centre for Atomic Research, Kalpakkam
Author in the following contributions
- Progress in the Design and R&D for future FBRs
- Thermal Hydraulic Simulation of Loss of Flow Without Scram Test in FFTF using DYANA-P code
- Modeling and Simulation of Source Term for Sodium-Cooled Fast Reactor under Hypothetical Severe Accident: Sodium Fire and Radionuclide Transport in Containment
- Thermal hydraulic assessment of the performance of secondary sodium system based decay heat removal circuit
- Design of metal fuel pin for test irradiation in FBTR and for future reactors.
- Root Cause Analysis of FBTR Failed Fuel Pin
- DEVELOPMENT OF COOLANT VOIDING MODEL FOR FAST REACTOR CORE
- DESIGN & ANALYSIS OF A NOVEL ARRANGEMENT FOR COUPLING AND DECOUPLING OF ROTATABLE PLUGS IN PFBR
- DESIGN & DEVELOPMENT OF CUSTOM SHAPED BACK-UP SEAL IN SILICONE FOR PFBR
- AN EXPERIMENTAL STUDY ON SECONDARY SODIUM SYSTEM BASED DECAY HEAT REMOVAL CIRCUIT OF A SODIUM COOLED FAST REACTOR
- 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
- Design Studies Towards Raising FBTR to Full Power
- DESIGN, MANUFACTURING AND IN-SODIUM TESTING OF AM350-WELDED DISC BELLOWS FOR FBTR CONTROL ROD DRIVE MECHANISM
