Solution target for cyclotron production of radiometals
Methods of producing and isolating 68 Ga, 89 Zr, 64 Cu, 63 Zn, 86 Y, 61 Cu, 99m Tc, 45 Ti, 13 N, 52 Mn, or 44 Sc and solution targets for use in the methods are disclosed. The methods of producing 68 Ga, 89 Zr, 64 Cu, 63 Zn, 86 Y, 61 Cu, 99m Tc, 45 Ti, 13 N, 52 Mn, or 44 Sc include irradiating a closed target system with a proton beam. The closed target system can include a solution target. The methods of producing isolated 68 Ga, 89 Zr, 64 Cu, 63 Zn, 86 Y, 61 Cu, 99m Tc, 45 Ti, 52 Mn, or 44 Sc further include isolating 68 Ga, 89 Zr, 64 Cu, 63 Zn, 86 Y, 61 Cu, 99m Tc, 45 Ti, 52 Mn, or 44 Sc by ion exchange chromatography. An example solution target includes a target body including a target cavity for receiving the target material; a housing defining a passageway for directing a particle beam at the target cavity; a target window for covering an opening of the target cavity; and a coolant gas flow path disposed in the passageway upstream of the target window.
1. A method for producing a solution including a radionuclide, the method comprising:
(a) bombarding a target solution comprising an aqueous solution of a nitrate salt of a metal in the presence of dilute nitric acid in a target cavity of a solution target with protons to produce a solution including a radionuclide, wherein the radionuclide is 68 Ga,
wherein the target cavity is cooled with a coolant during the bombardment.
2. The method of claim 1 , wherein the target solution is bombarded with protons in the target cavity of the solution target operating as a closed system.
3. The method of claim 2 , wherein the solution target has a volume capacity of two milliliters or less.
4. The method of claim 2 , wherein the target cavity is defined by a generally conical wall and a target window foil.
5. The method of claim 1 , wherein the target solution comprises 68 Zn-enriched zinc nitrate.
6. The method of claim 1 wherein the concentration of nitric acid in the target solution is 0.1 M to 2 M.
7. The method of claim 1 , wherein step (a) comprises bombarding the target solution with a particle beam having an energy of 15 MeV or less.
8. The method of claim 1 , further comprising:
(b) passing the solution including the radionuclide through a column including a sorbent to adsorb the radionuclide on the sorbent; and
(c) eluting the radionuclide off the sorbent.
9. The method of claim 8 , wherein the sorbent comprises a hydroxamate resin.
10. The method of claim 8 , wherein step (c) comprises eluting the radionuclide off the sorbent using a phosphate.
11. The method of claim 8 , wherein the radionuclidic purity of the radionuclide is greater than 99% after step (c).
12. The method of claim 8 , further comprising:
(d) passing the eluted radionuclide through a second column including a sorbent.
13. The method of claim 8 , wherein step (c) comprises eluting the radionuclide off the sorbent at a pH of 3.5 to 7.