Thrust areas
include
| Thermal hydraulic studies for PHWR, AHWR, CHTR, Supercritical Systems, Molten Salts and Nanofluids |
Design, development of passive valves, custom-made sensors |
Multi-scale material modelling and mockup facility |
Material property evaluation by Miniature Specimen Testing |
Reactor Physics design of AHWR, CHTR and IHTR |
Studies on Parallel Channel Instability and Natural circulation |
Development of Coupled Neutronics and Thermal hydraulic phenomena |
Reactor containment design studies |
Structural integrity assessment studies: Leak-before-break, Master Curve, Fatigue, fracture and ratchetting |
Seismic studies: Seismic response reduction using Dampers, Pushover Technique, Shake table testing of structures, Piping and equipment |
Probabilistic Safety Assessment, Reliability and Fire Safety |
Impact analysis and testing for qualification of radioactive material shipping casks |
Hydrogen mitigation |
Safety evaluation of nuclear power plants and facilities |
Severe accident analysis and management guidelines |
Design & development of the High Flux Reactor |
Robotics & remote handling. |
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The Indian Nuclear Power Programme today comprises existing reactors, reactors under construction, and planning and design of future reactors which will provide long term energy security to the country. R&D activities in BARC in the area of nuclear power began with the construction and operation of research reactors. Today, BARC operates two research reactors Dhruva and the AHWR Critical Facility. These are used for Neutron Beam Research, Fuel and Material Irradiation, Radioisotope Production, Neutron Radiography and Reactor Physics experiments.
Under the Three-stage Indian Nuclear Power Programme, R&D on existing current generation reactors includes: Ageing management and life extension of currently operating reactors, Development of in-service inspection systems, such as BARCIS (BARC Channel Inspection System) and the Periscope for the Prototype Fast Breeder Reactor (PFBR), Development of remotely operable man-rem saving tools and systems, Assessment of residual life of components, On-line monitoring of integrity of systems, Replacement of aged components / systems and R&D for Pressurized Heavy Water Reactors (PHWRs). BARC is involved in the design & development of the fuel handling system for the PFBR.
The Advanced Heavy Water Reactor (AHWR) (proliferation resistant with passive safety features, being developed with the aim of Thorium utilization), the Compact High Temperature Reactor (CHTR), the Indian High Temperature Reactor (IHTR) and the Accelerator Driven Subcritical System (ADSS) are part of R&D on future reactors, which envisage that besides electricity, nuclear energy would play a significant role in the production of alternate transportation fuel such as hydrogen, by splitting of water. Technologies for high temperature nuclear reactors capable of supplying process heat at a temperature of around 1000°C are also being developed.
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BARC Channel Inspection system in operation at the Tarapur Atomic Power Station - 4
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Core cross-sectional layout of the Compact High Temperature Reactor (CHTR)
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