Abstract
The central goal of this design is to meet U.S. demand for the medical isotope 99Mo with a water-cooled critical reactor featuring discrete, cladded fuel elements. 99Mo is produced within the solid fuel that is powering the fission reaction. The fuel is a low-enriched uranyl nitrate hexahydrate crystal, chosen to take advantage of a flexible uranium recovery process. The low melting temperature of the fuel material has required utilizing an annular fuel pin geometry. Preliminary heat transfer calculations and MCNP modeling have demonstrated the capability of such a design to produce the desired quantities of 99Mo.
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Schedule a callMore From: Journal of Radioanalytical and Nuclear Chemistry Letters
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