The thorium cycle for fast breeder reactors

Ramanna, R. ; Lee, S. M. (1986) The thorium cycle for fast breeder reactors Pramana - Journal of Physics, 27 (1-2). pp. 129-137. ISSN 0304-4289

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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.

Item Type:Article
Source:Copyright of this article belongs to Indian Academy of Sciences.
Keywords:Thorium Cycle; Fast Breeder Reactors; Nuclear Physics Features
ID Code:36093
Deposited On:12 Apr 2011 11:10
Last Modified:17 May 2016 19:03

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