Patent Application
20110214995
The present disclosure relates to a method for making radioactive isotopic gallium-67 and, more particularly, to a method for rapidly filtering pure gallium-67 liquid.
Gallium-67 (67Ga) is a radioactive isotope produced by a cyclotron. The nuclear properties of gallium-67 are short half life (t1/2=78 h) and medium energy (E.C.=100%, Er=93 KeV (38%), 185 KeV (23.6%) and 300 KeV (19%)). Therefore, gallium-67 is often used in single photon emission computerized tomography (“SPECT”) for human organs. Substantial nuclear reaction in the production of gallium-67 includes 68Zn (p, 2n), 67Zn (d, 2n) and 65Cu (α, 2n). The yield of the production of gallium-67 is highest if high-concentration zinc-68 (higher than 97%) with proper thickness (0 to 100 μm) is used as a target subject to proper proton irradiation (0 to 22 Mev). By dissolving the irradiated target and chemical separation, carrier-free gallium-67 chloride and citrate are provided. The carrier-free gallium-67 chloride and citrate can be combined with other organic ligands and turned into nuclear medicine for medical treatment. However, the radioactive isotopes cannot be produced in Taiwan, and all of the gallium-68 necessary for the production of the nuclear medical citrate is imported difficultly, expensively.
The present disclosure is therefore intended to obviate or at least alleviate the problems encountered in prior art.
It is the primary objective of the present disclosure to provide a method for making radioactive isotopic gallium-67.
To achieve the foregoing objective, isotopic zinc-68 is turned into a zinc-68 solid target by disposition or electroplating. Then, the zinc-68 solid target is subjected to proton irradiation. The irradiated zinc-68 solid target is dissolved in strong acid and turned into solution that contains zinc-65, zinc-68, gallium-67 and gallium-68. Hydrochloric acid and resin are added into the solution for exchange of ions. Zinc-68 solution and gallium-67 solution are separated from the solution by filtering. The gallium-67 solution is evaporated, thus providing radioactive isotopic gallium-67.
Other objectives, advantages and features of the present disclosure will be apparent from the following description referring to the attached drawings.
The present disclosure will be described via detailed illustration of the preferred embodiment referring to the drawings wherein:
Referring to
At 11, zinc-68 is turned into a zinc-68 solid target 21 by electroplating.
At 12, the zinc-68 solid target 21 is subjected to proton irradiation in a cyclotron (not shown). The intensity of the proton irradiation in the cyclotron is 15 to 40 MeV.
At 13, the irradiated zinc-68 solid target 21 is dissolved in strong acid in the dissolving unit 2. Thus, there is provided solution containing zinc-68, gallium-66, gallium-67 and gallium-68. The strong acid can be hydrochloric acid with concentration of 8N to 12N and preferably 9N.
At 14, some of the solution is filled in the ion-exchange column 3. Hydrochloric acid, with concentration of 8N to 12N and preferably 9N, and resin are filled in the ion-exchange column 3 for ion exchange. Gallium-67 solution 41 is absorbed. Zinc-68 solution 311 is sent into the zinc-68 solution-recycling bottle 31. Low-concentration solution 32 is transferred into the waste liquid-recycling unit 32.
At 15, the gallium-67 solution is heated in an evaporation unit 4, so that the hydrochloric acid is evaporated and then radioactive isotopic gallium-67 is made.
The present disclosure has been described via the detailed illustration of the preferred embodiment. Those skilled in the art can derive variations from the preferred embodiment without departing from the scope of the present disclosure. Therefore, the preferred embodiment shall not limit the scope of the present disclosure defined in the claims.
