US3664964A

US3664964A - Eluent for radioisotopes

Info

Publication number: US3664964A
Application number: US742128A
Authority: US
Inventors: Thomas A Haney; Gerald A Bruno
Original assignee: ER Squibb and Sons LLC
Current assignee: ER Squibb and Sons LLC
Priority date: 1968-07-03
Filing date: 1968-07-03
Publication date: 1972-05-23
Anticipated expiration: 1989-05-23
Also published as: DE1929067A1; GB1280537A; BE735608A; CA929685A; FR2012258A1; CS161858B2; ES369006A1; NL6910212A; CH501425A

Abstract

This disclosure relates to an eluent which improves the yield of nuclear radioisotopes from ion exchange resins. The disclosure in essence concerns itself with the addition of an oxidizing agent to an isotonic saline solution, said oxidizing agent being present in a concentration of from about 0.001 percent to about 1.0 percent on a volume/volume ratio.

Description

United States Patent Haney et a1.

451 May23, 1972 ELUENT FOR RADIOISOTOPES lnventors: Thomas A. Haney, East Brunswick; Gerald A. Bruno, Shrewsbury, both of NJ.

Assignee: E. R. Squibb & Sons, Inc., New York,

Filed: July 3, 1968 Appl. No.: 742,128

U.S. Cl ..252/364, 23/338, 210/31, 252/301.1 R

Int. Cl. ..B0lf l/00, C22b 61/04 Field of Search ..252/364, 95; 23/50 BE, 338; 210/31 C References Cited UNlTED STATES PATENTS 2,780,514 2/1957 Lutz ..23/338 3,002,823 10/1961 Flodin et al.. ...2l0/3l X 3,393,153 7/1968 Zimmerer et al. ..252/95 Primary ExaminerRichard D. Lovering Attorney-Lawrence S. Levinson and Merle J. Smith [57] ABSTRACT 4 Claims, No Drawings ELUENT FOR RADIOISOTOPES In recent years radioactive isotopes such as lodine Technetium 99", Yttrium, and many others, such as l-131, ST-85, Sr--87" and P-32, have been used in the medical and biological fields as tracer elements for investigative and diagnostic purposes and in some cases as a therapeutic agent. Many of these radioactive isotopes are delivered to the user by means of a generator, wherein the radioactive isotope is contained on an ion exchange resin in its parent form. By utilizing the proper eluent one is able to separate the daughter isotope from the parent which is adsorbed on an ion exchange resin. The generator thus utilized has become known to the art as a cow and the operation of eluting the daughter isotope from its parent has become known as a milking" process.

Recently, new sterile generators which are sterile and nonpyrogenic have been developed and are presently on the market. The milking of these generators is different in that hypodermic needles and syringes must be utilized and a sterile condition maintained throughout the operation. However, the present invention relates to both non-sterile and sterile generators.

It has been discovered that by the addition of an oxidizing agent to an eluent solution, the yield of the daughter isotope is significantly increased.

The eluent in this invention is a saline solution which is prepared by methods known to the art. The saline solution may be 0.9 percent sodium chloride solution or an isotonic sodium chloride solution. The oxidizing agent added to this solution may be oxygen (bubbling it through the solution), an alkali metal hypochlorite (e.g., sodium hypochlorite), an alkali metal permanganate (e.g., potassium permanganate), ferthe radioisotope to be separated or eluted from the generator. The method of utilizing the modified eluent of this invention is the same as customarily utilized in eluting generators whether they be of the sterile of non-sterile type.

The following examples illustrate the utilization of the eluent in the separation of various radioisotopes. In these examples all degrees are in Centigrade, unless otherwise stated:

EXAMPLES 1 TO 20 The following solutions are prepared by procedures known to the art, except as otherwise stated:

Solution A Normal isotonic saline with parabens.

Solution B 0.9% Sodium chloride solution.

Solution C 0.9% Sodium chloride solution with 0.5%

available chlorine pH 5.3.

Solution D 0.9% Sodium chloride solution with 0.5%

available chlorine pH 4.5.

Solution E 0.9% Sodium chloride with 0.01% available chlorine H 5.5. Solutions C, and E which are isotonic chlorine saline solu- TABLE 1 [Tc yield using various eluting solutions] Generator MC Milking 'Ic T0 o Potency eluent MC /25 percent MO Gen. Milking assayed label solution ml. of label content 128 100 B 105 105 N one. 2 100 78 B 72 92 Do. 100 1110..-- 78 61 B 52 85 Do. 4 61 47 D0. 47 37 E 34. 2 92 D0. is 316 200 B 130 65 Do. 2 246 156 B 70 Do. 200 mc 192 122 B 47 39 Do. 4 150 95 Do. 117 74 E )5 128 Do. 560 421 A 365 87 Do. 2d 266 200 A 11 5. 5 D0. 200 me, 2d (i'e milk) 266 200 C 165 83 Do. 3d 207 156 A 170 10!] Do. 162 122 A 110 00 D0. 790 632 A 416 66 Do. 375 300 A 13 4. 3 D0. 300 m(. 293 234 A 23 10 D0. 4 h 288 183 A 21 11.5 D0. 4th (re milk) 288 183 D 110 60 Do.

ric chloride, hydrogen peroxide and an alkali metal perhalogenate (e.g., potassium perchloride, sodium perbromide, and so forth). It is to be understood that both organic and inorganic oxidizing agents, such as peracetic acids, cupric acetate, iodoisobenzene, phenanthrenequinone, and pyridine N-oxide may also be utilized in the practice of this invention.

It has been found that a pH of the eluent of from about 3.0 to about 7.0 is effective. However, superior results were obtained when the eluent was maintained at a pH of from about 4 to about 6.8 with the best results being observed when the pH of the eluate was from about 5 to about 6.5.

The concentration of the oxidizing agent on a v/v basis should be in the range of from about 0.01 percent to 0.1 percent. However, depending upon the oxidizing agent utilized, a concentration in the range of from about 0.001 percent to about 1 percent may be preferable. However, it has been discovered that extremely satisfactory results are obtained when the concentration of the oxidizing agent is in the range on a v/v basis of from about 0.02 percent to about 0.05 percent.

As indicated above the initial eluent may be sterilized water, sterilized saline solution, an acid eluent or basic eluent depending upon the ion exchange resin utilized in the cow and From the above Table it is established that the yield of Technetium 99" can be significantly increased by utilizing isotonic chlorine water.

The invention may be variously otherwise embodied within the scope of the appended claims.

What is claimed is:

1. An eluent solution for use in eluting radioactive isotopes from an ion exchange resin consisting essentially of an isotonic saline solution and an oxidizing agent said oxidizing agent being present in a concentration of from about 0.001 percent to about 1.0 percent on a volume/volume ratio.

2. An eluent in accordance with claim 1 wherein the oxidizing agent is selected from the group consisting of oxygen, an alkali metal hypochlorite, an alkali metal permanganate, an alkali metal perhalogenate, ferric chloride, hydrogen peroxide, peracetic acids, cupric acetate, iodoisobenzene, phenanthrene-quinone and pyridine N-oxide.

3. An eluent in accordance with claim 1 wherein the pH of the eluent is from about 3.0 to about 7.0.

4. An eluent in accordance with claim 1 wherein the oxidizing agent is present in a concentration of from about 0.01 percent to 0. 1 percent on a volume/volume ratio.

Claims

2. An eluent in accordance with claim 1 wherein the oxidizing agent is selected from the group consisting of oxygen, an alkali metal hypochlorite, an alkali metal permanganate, an alkali metal perhalogenate, ferric chloride, hydrogen peroxide, peracetic acids, cupric acetate, iodoisobenzene, phenanthrene-quinone and pyridine N-oxide.
3. An eluent in accordance with claim 1 wherein the pH of the eluent is from about 3.0 to about 7.0.
4. An eluent in accordance with claim 1 wherein the oxidizing agent is present in a concentration of from about 0.01 percent to 0.1 percent on a volume/volume ratio.