Fuel Cycle Flexibility in Advanced Heavy Water Reactor (AHWR) with the use of Th-LEU Fuel
International Conference on the Future of Heavy Water Reactors - 2011 October 02-05

Presented at:
International Conference on the Future of Heavy Water Reactors
2011 October 02-05
Ottawa, Canada
Session Title:
Thorium Fuel

Amit Thakur (Bhabha Atomic Research Centre)
Baltej Singh (Bhabha Atomic Research Centre)
Neelima Prasad Pushpam (Bhabha Atomic Research Center)
Vishal Bharti (Bhabha Atomic Research Centre)
Umasankari Kannan (Bhabha Atomic Research Centre)
Pritam Das Krishnani (Bhabha Atomic Research Centre)
R.K. Sinha (Bhabha Atomic Research Centre)


The Advanced Heavy Water Reactor (AHWR) is being designed for large scale commercial utilization of thorium (Th) and integrated technological demonstration of the thorium cycle in India. The AHWR is a 920 MW(th), vertical pressure tube type cooled by boiling light water and moderated by heavy water. Heat removal through natural circulation and on-line fuelling are some of the salient features of AHWR design. The physics design of AHWR offers considerable flexibility to accommodate different kinds of fuel cycles. Our recent efforts have been directed towards a case study for the use of Th-LEU fuel cycle in a once-through mode. The discharged Uranium from Th-LEU cycle has proliferation resistant characteristics. This paper gives the initial core, fuel cycle characteristics and online refueling strategy of Th-LEU fuel in AHWR.

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