The thorium cycle for fast breeder reactors |
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Authors: | R Ramanna S M Lee |
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Institution: | (1) Department of Atomic Energy, Chhatrapati Shivaji Maharaj Marg, 400 039 Bombay, India |
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Abstract: | The role that could be played by liquid metal-cooled fast breeder reactors (LMFBRs) in the utilization of India’s considerable
thorium resources is reviewed in this article. Distinct advantages of thorium-based fuels over plutonium-uranium fuels in
LMFBRs pertain to a more favourable coolant voiding reactivity coefficient and better fuel element irradiation stability.
The poorer breeding capability of thorium-fuelled fast reactors can in principle be overcome by improved core design and development
of advanced fuel concepts. The technical feasibility of such advanced thorium fuels and core designs must be established by
sustained research and development. It is also necessary to efficiently close the thorium fuel cycle of fast breeder reactors
by appropriate development of the fuel reprocessing and refabrication stages. The Fast Breeder Test Reactor (FBTR) at Kalpakkam
is expected to be an important tool for development of thorium fuel and fuel cycle technology. A quick look at the economics
of the thorium cycle for fast reactors, vis-a-vis the more conventional uranium cycle indicates only a small and acceptable
cost disadvantage on account of the need for remote fabrication of recycled thorium fuel.
The authors felicitate Prof. D S Kothari on his eightieth birthday and dedicate this paper to him on this occasion. |
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Keywords: | Thorium cycle fast breeder reactors nuclear physics features |
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