Multiple generator elution system

Abstract

A multiple generator elution system for selectively eluting from a plurality of parent-daughter generators according to an elution schedule it calculates taking into account supply data, demand data, and available activity in each of the generators.

Description

FIELD OF THE INVENTION[0001]The present invention relates to the field of radioisotope generators. More specifically, the present invention is directed to a multiple generator elution system.BACKGROUND OF THE INVENTION[0002]Fission-produced Mo-99 supply is in a state of uncertainty. Only two reactors, the Canadian NRU reactor and the Petten HFR reactor, represent approximately 60-70% of the world's supply of fission produced Mo-99. When either of these reactors goes off-line, whether for scheduled maintenance or for unscheduled repairs, the result is to effectively reduce nuclear medicine procedures to only essential cases. All the reactors used to manufacture fission Mo-99 are nearing the end of their respective working lives, currently only one replacement reactor is planned, the Petten replacement called Pallas. Of additional concern is the proliferation of highly enriched uranium (HEU), the target material for fission Mo-99, falling into the hands of terrorists or rogue governme...

AI Technical Summary

Benefits of technology

The present invention provides a multiple generator elution system that tracks the grow-in of the activity of each parent-daughter nucleus generator and schedules elution from among the generators to meet an inputted demand for the daughter nuclide. The system includes a control system that receives demand data indicating requirements for activity production and elutes from selected generators to meet the demand. The system also includes a concentration column for collecting the generator daughter nuclide from the selected generators. The control system automatically manages the isotope "grow-in" for maximum efficiency and cost savings. The invention allows a gamma gel based Mo-99 generator to be more operationally competitive with fission based generators, thus reducing the proliferation of nuclear bomb grade material. The invention also provides a kit for a manifold system and a method for operating the system. The technical effects of the invention include improved efficiency, cost savings, and reduced proliferation of nuclear bomb grade material.

Problems solved by technology

Unfortunately, Mo-99 produced from n,γ methods tends to be of low specific activity when compared to Mo-99 produced from fission of U-235, whether HEU or low enriched uranium (LEU).

The prior art fails to address all of the issues encountered with low specific activity and or low activity generators.

This is a complicated procedure that requires the use of organic solvents (tetrabutylammonium bromide solution in methylene chloride) to extract and concentrate the Tc-99m.

This method is impractical because of time required to prepare the concentrated Tc-99m.

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