U.S. patent application number 12/718826 was filed with the patent office on 2011-09-08 for method for making radioactive isotopic gallium-67.
This patent application is currently assigned to ATOMIC ENERGY COUNCIL-INSTITUTE OF NUCLEAR ENERGY RESEARCH. Invention is credited to Jenn-Tzong Chen, Sun-Rong Huang, Wuu-Jyh Lin, Jainn-Hsin Lu, Ying-Ming Tsai.
Application Number | 20110214995 12/718826 |
Document ID | / |
Family ID | 44530366 |
Filed Date | 2011-09-08 |
United States Patent
Application |
20110214995 |
Kind Code |
A1 |
Huang; Sun-Rong ; et
al. |
September 8, 2011 |
Method for Making Radioactive Isotopic Gallium-67
Abstract
Disclosed is a method for making carrier-free radioactive
isotopic gallium-67. Stable isotopic zinc-68 is turned into zinc-68
solid target by disposition or electroplating. Then, the zinc-68
solid target is subjected to a proton beam. A cyclotron is used to
provide irradiation from 15 to 40 MeV. After the irradiation, the
zinc-68 solid target is dissolved in concentrated acid and turned
into solution that contains zinc-65, zinc-68, gallium-67 and
gallium-68. High concentrated hydrochloric acid and resin are added
into the solution for exchange of ions. Zinc-68 liquid and
gallium-67 liquid are filtered and separated from the solution.
Thus, pure gallium-67 liquid is produced. With a vaporizer, the
gallium-67 liquid is vaporized and turned into radioactive isotopic
gallium-67.
Inventors: |
Huang; Sun-Rong; (Taoyuan
County, TW) ; Tsai; Ying-Ming; (Taoyuan County,
TW) ; Lu; Jainn-Hsin; (Taoyuan County, TW) ;
Chen; Jenn-Tzong; (Taipei City, TW) ; Lin;
Wuu-Jyh; (Taoyuan County, TW) |
Assignee: |
ATOMIC ENERGY COUNCIL-INSTITUTE OF
NUCLEAR ENERGY RESEARCH
Taoyuan County
TW
|
Family ID: |
44530366 |
Appl. No.: |
12/718826 |
Filed: |
March 5, 2010 |
Current U.S.
Class: |
205/340 |
Current CPC
Class: |
Y02P 10/20 20151101;
Y02P 10/234 20151101; C25C 1/22 20130101 |
Class at
Publication: |
205/340 |
International
Class: |
C25C 1/22 20060101
C25C001/22 |
Claims
1. A method for making carrier-free radioactive isotopic
gallium-67, the method comprising the steps of: turning isotopic
zinc-68 into a zinc-68 solid target by electroplating; subjecting
the zinc-68 solid target to proton irradiation; dissolving the
zinc-68 solid target in strong acid, thus providing solution that
contains zinc-65, zinc-68, gallium-67 and gallium-68; adding
hydrochloric acid and resin in the solution for exchange of ions;
filtering the solution, thus providing zinc-68 solution and
gallium-67 solution; and evaporating the gallium-67 solution, thus
providing radioactive isotopic gallium-67.
2. The method according to claim 1, wherein the intensity of the
proton irradiation is 15 to 40 MeV.
3. The method according to claim 1, wherein the strong acid used to
dissolve the zinc-68 solid target is hydrochloric acid with
concentration of 8N to 12N.
4. The method according to claim 1, wherein the concentration of
the hydrochloric acid added in the solution is 8N to 12N.
Description
TECHNICAL FIELD
[0001] 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.
DESCRIPTION OF THE RELATED ARTS
[0002] Gallium-67 (.sup.67Ga) is a radioactive isotope produced by
a cyclotron. The nuclear properties of gallium-67 are short half
life (t.sub.1/2=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 .sup.68Zn (p, 2n), .sup.67Zn (d,
2n) and .sup.65Cu (.alpha., 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 .mu.m) 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.
[0003] The present disclosure is therefore intended to obviate or
at least alleviate the problems encountered in prior art.
SUMMARY OF THE DISCLOSURE
[0004] It is the primary objective of the present disclosure to
provide a method for making radioactive isotopic gallium-67.
[0005] 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.
[0006] Other objectives, advantages and features of the present
disclosure will be apparent from the following description
referring to the attached drawings.
BRIEF DESCRIPTIONS OF THE DRAWINGS
[0007] The present disclosure will be described via detailed
illustration of the preferred embodiment referring to the drawings
wherein:
[0008] FIG. 1 is a flow chart of a method for making radio isotopic
gallium-67 according to the preferred embodiment of the present
disclosure; and
[0009] FIG. 2 is a scheme of equipment used in the method shown in
FIG. 1 to make radio isotopic gallium-67.
DESCRIPTION OF THE PREFERRED EMBODIMENT
[0010] Referring to FIG. 1, there is shown a method for making
radioactive isotopic gallium-67 according to the preferred
embodiment of the present disclosure. Referring to FIG. 2, there is
shown equipment used in the method to make radioactive isotopic
gallium-67. The equipment includes a dissolving unit 2, an
ion-exchange column 3, a zinc-68 solution-recycling unit 31, a
waste liquid-recycling unit 32 and an evaporation unit 4.
[0011] At 11, zinc-68 is turned into a zinc-68 solid target 21 by
electroplating.
[0012] 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.
[0013] 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.
[0014] 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.
[0015] 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.
[0016] 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.
* * * * *