• R&D pertaining to structural, thermal-hydraulics and probabilistic safety of Indian NPPs
• Fracture, fatigue & creep assessment of nuclear structural components
• Development of severe accident management guidelines and computer code PRABHAVINI
• Thermal-hydraulic safety analysis for Indian NPPs
• Multi-scale material modeling to determine mechanical properties of aged materials
• Core and containment safety studies
• Probabilistic safety analysis and reliability studies for nuclear facilities
• Seismic and civil design of structures of nuclear facilities
The accident source term code PRABHAVINI v2.0 is released in March 2020. The released version 2.0 has five major modules namely PRAVAH (thermal-hydraulics), ABHA (Core Degradation), PARIVAHAN (fission-product transport), PARIRODHAN (Containment phenomena) and PURAK (system components). ABHA contains sub-modules SHAKTI (Point Kinetics), PARIRODHAN contains two sub-modules VAHITI (Containment thermal-hydraulics) and DAHAN (hydrogen combustion).
Facilities have been designed, developed and are in operation to carry out (i) thermal ageing (under accelerated conditions up to 300deg Cel), (ii) Humidity Chamber - temperature range from ambient to 80 deg Cel and maximum relative humidity up to 95±5% (iii) radiation ageing - dose rate 0.1MRad/hr , (iv) Loss of Coolant Accident (LOCA) environment - Maximum steam temperature and pressure achievable inside the LOCA chamber are 150 deg Cel and 3.4 kg(g) (50 psig) respectively (v) Main Steam Line Break qualification studies of C&I components and equipment - 171deg C and 32 psig.
Facilities have been designed, developed and are in operation to carry out (i) thermal ageing (under accelerated conditions up to 300deg Cel), (ii) Humidity Chamber - temperature range from ambient to 80 deg Cel and maximum relative humidity up to 95±5% (iii) radiation ageing - dose rate 0.1MRad/hr , (iv) Loss of Coolant Accident (LOCA) environment - Maximum steam temperature and pressure achievable inside the LOCA chamber are 150 deg Cel and 3.4 kg(g) (50 psig) respectively (v) Main Steam Line Break qualification studies of C&I components and equipment - 171deg C and 32 psig.
