FIELD: metallurgy.
SUBSTANCE: production of Mo-99 consists in filling solution reactor with fuel solution of uranyl-sulphate, in starting reactor up to specified power, in forming Mo-99 in fuel solution, in reactor shut-down, in conditioning fuel solution for decay of short-lived radionuclide and in sorption of Mo-99 from solution. Also, after reactor shut-down fuel solution is poured out of the reactor into at least one nuclear-safe reservoir; fuel solution is conditioned in this nuclear-safe reservoir. An empty reactor is repeatedly filled with fuel solution, is started up to specified power and Mo-99 is repeatedly generated in fuel solution. For the period of Mo-99 generation in the fuel reactor poured fuel solution in the nuclear-safe reservoir is conditioned. Mo-99 is sorbed from conditioned fuel solution by pumping it through at least one sorption column wherefrom Mo-99 is sorbed into at least one nuclear-safe reservoir for fuel solution conditioning. Fuel solution is conditioned, if necessary. Repeatedly emptied reactor is filled with fuel solution from the nuclear-safe reservoir for fuel solution conditioning.
EFFECT: raised efficiency of solution reactor producing Mo-99 under discrete mode due to reduced idle time.
9 cl, 1 dwg, 1 ex
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Authors
Dates
2011-02-27—Published
2009-12-03—Filed