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ahwr barc |
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Re: ahwr barc
N BARC the Development of Advanced Heavy Water Reactor, AHWR300-LEU, is an effort to realise these futuristic objectives through innovative configuration of present day technologies. The Indian Advanced Heavy Water Reactor (AHWR) is being designed and developed to achieve large-scale use of thorium for the generation of commercial nuclear power. This reactor will produce most of its power from thorium, with no significant external input of uranium-233, in the equilibrium cycle Advanced Heavy Water Reactor of Bhabha Atomic Research Centre Important Design Parameters of AHWR: Reactor power 920 MWTh Core configuration Vertical, pressure tube type design Coolant Boiling light water Number of coolant channels 452 Pressure tube ID 120 mm Lattice pitch 270 mm (square pitch) No. of pins in fuel cluster 54 (Th-Pu)O2 - 24 pins (Th-U)O2 - 30 pins Pin OD 11.2 mm Heated fuel length 3.5 m Total core flow rate 2175 kg/s Coolant inlet temperature 259 oC (nominal) Feed water temperature 130 oC Average steam quality 19 % Steam generation rate 414 kg/s Steam drum pressure 70 bar PHT loop height 39 m Calandria diameter 8000 mm Calandria height 5000 mm Contact to: Reactor Design & Development Group, Bhabha Atomic Research Centre, Trombay, Mumbai - 400 085 India |
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