Home
» R & D » Advanced Reactor Technologies & Nuclear Power
  ADVANCED REACTOR TECHNOLOGIES AND NUCLEAR POWER

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.

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.

Click the image for bigger view
BARC Channel Inspection system in operation

BARC Channel Inspection system in operation at the Tarapur Atomic Power Station - 4

Click the image for bigger view
Core cross-sectional layout of the Compact High Temperature Reactor (CHTR)

Core cross-sectional layout of the Compact High Temperature Reactor (CHTR)

Click the image for bigger view
ARCOM at 1:4 size containment test model at Tarapur built to generate database of containment performance evaluation studies and failure modes

BARCOM at 1:4 size containment test model at Tarapur built to generate database of containment performance evaluation studies and failure modes

Click the image for bigger view
Pressurized pipe undergoing

Pressurized pipe undergoing a Shaketable Test