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- W1486010431 abstract "A fluid fuel transmuter is proposed on the basis of circulating lead forming the fluid carrier material for long‐lived actinides. Thermalization of neutrons is achieved by the use of graphite in the blanket leading to low actinide concentrations, typically around 100 g/l. An eigenvalue of 0.95 is aimed at and the extraneous source neutrons are provided by the interaction of 1.6 GeV protons with a central lead target (spallation process). Fuel depletion and neutron transport calculations are discussed with a view to the technical feasibility and possible advantageous design modifications." @default.
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- W1486010431 date "1995-01-01" @default.
- W1486010431 modified "2023-09-26" @default.
- W1486010431 title "Design considerations and evaluations of an accelerator-driven fluid fuel transmuter" @default.
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- W1486010431 doi "https://doi.org/10.1063/1.49131" @default.
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