US3382152A - Production of high purity radioactive isotopes - Google Patents

Production of high purity radioactive isotopes Download PDF

Info

Publication number
US3382152A
US3382152A US399842A US39984264A US3382152A US 3382152 A US3382152 A US 3382152A US 399842 A US399842 A US 399842A US 39984264 A US39984264 A US 39984264A US 3382152 A US3382152 A US 3382152A
Authority
US
United States
Prior art keywords
radioactive
molybdenum
alumina
solution
column
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Expired - Lifetime
Application number
US399842A
Inventor
Lieberman Ephraim
Wayne J Gemmill
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Union Carbide Corp
Original Assignee
Union Carbide Corp
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Union Carbide Corp filed Critical Union Carbide Corp
Priority to US399842A priority Critical patent/US3382152A/en
Priority to GB25433/66A priority patent/GB1131546A/en
Priority to CH850866A priority patent/CH454805A/en
Priority to DE19661544156 priority patent/DE1544156A1/en
Priority to BE682978D priority patent/BE682978A/xx
Priority to FR66641A priority patent/FR1486542A/en
Application granted granted Critical
Publication of US3382152A publication Critical patent/US3382152A/en
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

Links

Classifications

    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G39/00—Compounds of molybdenum
    • C01G39/003—Preparation involving a liquid-liquid extraction, an adsorption or an ion-exchange
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G39/00—Compounds of molybdenum
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G99/00—Subject matter not provided for in other groups of this subclass
    • C01G99/006—Compounds containing, besides a metal not provided for elsewhere in this subclass, two or more other elements other than oxygen or hydrogen

Definitions

  • This invention relates to the production of high .purity radioactive isotopes, particularly molybdenum-99 and technetium-99m.
  • Technetttium-99m which has a half-life of six hours, is produced by the spontaneous radioactive beta decay of molybdenum-99. The latter has a half-life of 67 hours.
  • High purity Tc is used primarily as a radioisotope in medical research and diagnosis. It is well suited for liver and brain scanning, and is preferred over other radioactive isotopes because of its short half-life which results in reduced exposure of the organs to radiation.
  • radioactive molybdenum-99 has been recovered as a fission product formed by the fissioning of uranium-235 in a nuclear reactor.
  • This method of producing M0 has several important shortcomings.
  • Some of these fission products are long lived, and due to their radioactivity are difficult to handle without elaborate shielding.
  • a process which comprises irradiating a molybdenum containing material in the presence of a neutron flux until the desired amount of Mo activity is formed, dissolving the irradiated material (containing M0 in a base, adjusting the pH of the solution to be acidic and above pH 2.5, contacting an inorganic anion exchange material with the pH adjusted solution (thereby loading the molybdenum on the anion exchange material) and then selectively eluting or extracting technetium-99m, formed by the radioactive decay of molybdenum-99, from the loaded anion exchange material with an acid.
  • the present method offers several advantages over prior art methods of preparing technetium-99m.
  • One of these is elimination of the need to separate radioactive molybdenum from other radioactive fission products.
  • Another is a considerable reduction in the radioactive waste disposal problem.
  • a still further advantage of this invention is that a product of high purity is obtained containing no traces of other radioactive fission products.
  • the purity of T0 is of considerable importance because of its medicinal use.
  • EXAMPLE 0.38 gram of M00 were placed in a inch aluminum capsule and sealed. The capsule was irradiated for hours in a neutron flux of 5 x10 n/cm. -sec. The resulting material containing radioactive M0 had an activity of about 135 m-ilicuries. Folio-wing irradiation the M00 was dissolved in approximately 10 ml. of 40 percent NH,OH.
  • the solution of ammonium molybdate was first neutralized to a pH of 7 with 6 M HNO and then acidified to a pH of 3.0 to 3.5 with 1 M HNO Prior to loading the above radioactive solution on an alumina anion-exchange column, the column containing 6 grams of 100 to 200 mesh alumina was washed with water and 0.1 M HNO Effluent from th washing step was acidic (pH 2-6) before the column was loaded.
  • the solution of ammonium molybdate after having its pH adjusted to 3.0 to 3.5 (and which contains M0 was loaded on the alumina column at a flow rate of about l-2 ml. per min. After the column was loaded, it was Washed with about 150 ml. of 0.1 M HCl in order to remove the small quantities of M0 that would subsequently wash through during Tc elution and contaminate the product solution.
  • the loaded column which contained about milicuries of activity can subsequently be eluted or milked repeatedly for Tc as it is formed with 25 ml. portions of 0.1 M HCl solution. This is done by passing the desired volume of 0.1 M HCl through the column and collecting the efiluent.
  • M00 is the preferred target material for the production of M0 other molybdenum containing materials may be used.
  • Such materials include, for example, molybdenum sesquioxide, M0 0 molybdenum dioxide, M00 molybdenum pentoxide, M0 0 hydrated molybdenum oxide (moly blue), Mo -xH O; molybdic acid H MoO and mixtures thereof.
  • Separation of Tc from Mo can be efifected by contacting the M0 (in the form of molybdate ions) with alumina, followed by selective removal of Tc (in the form of the TcO, ion) from the loaded alumina.
  • a column of alumina is preferably used, however, the separation can be made by slurrying the molybdate ion containing solution with finely divided alumina in a container (thereby loading the alumina with molybdate ions), separating the solids from the liquid, for example, by filtration and then removing the T0 from the alumina particles by reslurrying the alumina in an acid and then separating the dissolved Tc" from the unloaded alumina solids.
  • Use of a column is, of course, far simpler and more etficient.
  • the material is referred to in this disclosure as an inorganic anion exchange material, it is to be understood that the materials rather than the mechanism whether ion exchange or adsorption are intended thereby.
  • Alumina is the preferred exchange material.
  • Other materials which are chemically stable in the system, stable to the radiation emitted in the system, and which are able to exchange the molybendum and technetium ions can be used in place of alumina.
  • Such materials include the inorganic refractory oxides of zirconium, thorium, tungsten and silicon. Suitable illustrative materials include Zirconia (ZrO thoria (ThO tungsten trioxide (W and silica (SiO These materials have an affinity for anions when their surfaces have been rendered acidic.
  • Bases other than NH OH may be used to dissolve the irradiated molybdenum containing material, provided they will not interfere with subsequent loading and elution of the inorganic anion-exchange material.
  • Suitable bases include, for example, NaOH and KOH. Ammonium hydroxide is preferred.
  • the solution be acidified and be above pH 2.5 At a pH below 2.5 precipitation results, while at an alkaline pH the molybdate ion will not load properly on the exchange material.
  • the preferred range is pH 3.0 to 3.5. Adjustment of the pH and washing of the exchange material is preferably done with HNO HCl is the preferred acid used for the preferential elution of Tc from the exchange material. ther mineral acids, however, such as HNO may also be used.
  • the amount of radiation to which the molybdenum containing target material is subjected is not critical and both the time and intensity of the neutron flux may be varied considerably from that shown in the preferred embodiment. It is merely necessary that the target material be irradiated until the desired amount of Mo activity is formed. A convenient amount is about 100-300 millicuries of Mo" per loaded column, or about 200-1000 millicuries per gram of irradiated M00 What is claimed is:
  • a process for producing radioactive technetium-99m which comprises the steps of:
  • step (3) (4) contacting an inorganic anion exchange material with the pH adjusted solution of step (3) thereby loading the molybdenum on the exchange material
  • a process for producing radioactive technetium-99m which comprises the steps of:
  • step (3) adjusting the pH of the solution formed in step (2) to be acidic and above pH 2.5,
  • step (2) 8. The process of claim 7 wherein the pH of the solution formed in step (2) is adjusted to be within the range of 3.0 to 3.5.
  • a process for producing radioactive technetium-99m which comprises the steps of:
  • step (3) contacting a column of alumina with the pH adjusted solution of step (2), thereby loading the column with molybdate ions, and
  • a process for producing radioactive technetium- 99rn which comprises the steps of:
  • a process for producing a solution containing radioactive molybdenum-99, from which solution radioactive molybdenum-99 can be loaded onto an inorganic anion exchange material comprises the steps of:
  • step (3) adjusting the pH of the solution formed in step (2) to be acidic and above pH 2.5.
  • a process for producing a solution containing radioactive molybdenum-99, from which solution radioactive molybdenum-99 can be loaded onto alumina comprises the steps of:
  • step (3) adjusting the pH of the solution prepared in step (2) to be within the range of 3.0 to 3.5.
  • a process for producing the combination comprising alumina having loaded thereon radioactive molybdenum-99 which process comprises the steps of:
  • step (2) (3) adjusting the pH of the solution formed in step (2) to be acidic and above pH 2.5, and
  • step (3) (4) loading the pH adjusted solution of step (3) on a column of alumina.
  • a process for producing the combination comprising alumina having loaded thereon radioactive molybdenum-99 which process comprises the steps of (1) irradiating M00 in a neutron flux until the desired amount of M0 activity is formed,
  • step (3) adjusting the pH of the solution prepared in step (2) to be within the range of 3.0 to 3.5, and
  • step (3) (4) loading the pH adjusted solution of step (3) on a column of alumina.

Landscapes

  • Chemical & Material Sciences (AREA)
  • Organic Chemistry (AREA)
  • Inorganic Chemistry (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)

Description

United States Patent 3,382,152 PRODUCTION OF HIGH PURITY RADIOACTIVE ISOTOPES Ephraim Lieberman, Suifern, N.Y., and Wayne J. Gemmill, Milford, Pa., assignors to Union Carbide Corporation, a corporation of New York No Drawing. Filed Sept. 28, 1964, Ser. No. 399,842
' 18 Claims. (Cl. 176-16) This invention relates to the production of high .purity radioactive isotopes, particularly molybdenum-99 and technetium-99m. Technetttium-99m, which has a half-life of six hours, is produced by the spontaneous radioactive beta decay of molybdenum-99. The latter has a half-life of 67 hours.
High purity Tc is used primarily as a radioisotope in medical research and diagnosis. It is well suited for liver and brain scanning, and is preferred over other radioactive isotopes because of its short half-life which results in reduced exposure of the organs to radiation.
Since the radioisotope sought to be used has such a short half-life, it is common practice to ship the users of the isotope the parent element; in this case M0 The user then extracts the Tc from the Mo as his needs require.
In the past, radioactive molybdenum-99 has been recovered as a fission product formed by the fissioning of uranium-235 in a nuclear reactor. This method of producing M0 has several important shortcomings. One is that the M0 has to be separated from the numerous other radioactive fission products of U-235 such as strontium-90, yttrium-91, zirconium-95, niobium-95, ruthenium-103, ruthenium-106, iodine-131, cerium-141, cesium-137, cerium-144, prometh-ium-l47 and many others. Some of these fission products are long lived, and due to their radioactivity are difficult to handle without elaborate shielding.
As a result of separation problems, pure molybdenum-99 and consequently pure Tc cannot be obtained from U-235 fissioning because traces of fission products such as iodine-131 and ruthenium-103 frequently remain in the separated product. In addition, this technique presents radioactive waste disposal problems.
It is an object of this invention to provide a more efficient method of producing radioactive molybdenum from which radioactive technetium may be extracted. It is another object of this invention to produce radioactive molybdenum by a method which avoids the need for separating radioactive fission products and avoids problems relating to disposing of radioactive waste resulting from the fissioning of U-235. It is another object of this invention to prepare high purity technetium-99 which contains no traces of fission products.
It has now been discovered that the aforementioned objects can be achieved by a process which comprises irradiating a molybdenum containing material in the presence of a neutron flux until the desired amount of Mo activity is formed, dissolving the irradiated material (containing M0 in a base, adjusting the pH of the solution to be acidic and above pH 2.5, contacting an inorganic anion exchange material with the pH adjusted solution (thereby loading the molybdenum on the anion exchange material) and then selectively eluting or extracting technetium-99m, formed by the radioactive decay of molybdenum-99, from the loaded anion exchange material with an acid.
The present method offers several advantages over prior art methods of preparing technetium-99m. One of these is elimination of the need to separate radioactive molybdenum from other radioactive fission products. Another is a considerable reduction in the radioactive waste disposal problem. A still further advantage of this invention is that a product of high purity is obtained containing no traces of other radioactive fission products. The purity of T0 is of considerable importance because of its medicinal use.
In order to more fully understand the invention, the following example, which is the preferred embodiment of the invention, is given by way of illustration only and is not intended to limit the scope of this invention.
EXAMPLE 0.38 gram of M00 were placed in a inch aluminum capsule and sealed. The capsule was irradiated for hours in a neutron flux of 5 x10 n/cm. -sec. The resulting material containing radioactive M0 had an activity of about 135 m-ilicuries. Folio-wing irradiation the M00 was dissolved in approximately 10 ml. of 40 percent NH,OH. The solution of ammonium molybdate was first neutralized to a pH of 7 with 6 M HNO and then acidified to a pH of 3.0 to 3.5 with 1 M HNO Prior to loading the above radioactive solution on an alumina anion-exchange column, the column containing 6 grams of 100 to 200 mesh alumina was washed with water and 0.1 M HNO Effluent from th washing step was acidic (pH 2-6) before the column was loaded. The solution of ammonium molybdate after having its pH adjusted to 3.0 to 3.5 (and which contains M0 was loaded on the alumina column at a flow rate of about l-2 ml. per min. After the column was loaded, it was Washed with about 150 ml. of 0.1 M HCl in order to remove the small quantities of M0 that would subsequently wash through during Tc elution and contaminate the product solution.
The loaded column which contained about milicuries of activity can subsequently be eluted or milked repeatedly for Tc as it is formed with 25 ml. portions of 0.1 M HCl solution. This is done by passing the desired volume of 0.1 M HCl through the column and collecting the efiluent.
Numerous variations of the preferred embodiment described above may be practiced, as will be apparent to those skilled in the art, without departing from the basic concepts of the present invention. Thus, while M00 is the preferred target material for the production of M0 other molybdenum containing materials may be used. Such materials include, for example, molybdenum sesquioxide, M0 0 molybdenum dioxide, M00 molybdenum pentoxide, M0 0 hydrated molybdenum oxide (moly blue), Mo -xH O; molybdic acid H MoO and mixtures thereof.
Separation of Tc from Mo can be efifected by contacting the M0 (in the form of molybdate ions) with alumina, followed by selective removal of Tc (in the form of the TcO, ion) from the loaded alumina. A column of alumina is preferably used, however, the separation can be made by slurrying the molybdate ion containing solution with finely divided alumina in a container (thereby loading the alumina with molybdate ions), separating the solids from the liquid, for example, by filtration and then removing the T0 from the alumina particles by reslurrying the alumina in an acid and then separating the dissolved Tc" from the unloaded alumina solids. Use of a column is, of course, far simpler and more etficient.
The exact nature of the exchange mechanism by which the molybdenum is loaded on alumina and by which the T0 is eluted is not entirely certain. While not wishing to be limited to any theory, it is believed to be an ion exchange mechanism whereby molybdate ions are loaded on the acidified alumina column in exchange for OH ions. Upon elution, the To is removed from the column as pertechnate, TcO ions in exchange for C1 ions. However, the ion exchange reaction appears to be limited to a surface phenomena, and it is therefore possible that the mechanism is actually a surface adsorption phenomena. It is most likely a combination of both ion exchange and adsorption. Thus, While the material is referred to in this disclosure as an inorganic anion exchange material, it is to be understood that the materials rather than the mechanism whether ion exchange or adsorption are intended thereby. Alumina is the preferred exchange material. Other materials, however, which are chemically stable in the system, stable to the radiation emitted in the system, and which are able to exchange the molybendum and technetium ions can be used in place of alumina. Such materials include the inorganic refractory oxides of zirconium, thorium, tungsten and silicon. Suitable illustrative materials include Zirconia (ZrO thoria (ThO tungsten trioxide (W and silica (SiO These materials have an affinity for anions when their surfaces have been rendered acidic.
Bases other than NH OH may be used to dissolve the irradiated molybdenum containing material, provided they will not interfere with subsequent loading and elution of the inorganic anion-exchange material. Suitable bases include, for example, NaOH and KOH. Ammonium hydroxide is preferred.
Following dissolution of the irradiated molybdenum containing material it is essential that the solution be acidified and be above pH 2.5 At a pH below 2.5 precipitation results, while at an alkaline pH the molybdate ion will not load properly on the exchange material. The preferred range is pH 3.0 to 3.5. Adjustment of the pH and washing of the exchange material is preferably done with HNO HCl is the preferred acid used for the preferential elution of Tc from the exchange material. ther mineral acids, however, such as HNO may also be used.
The amount of radiation to which the molybdenum containing target material is subjected is not critical and both the time and intensity of the neutron flux may be varied considerably from that shown in the preferred embodiment. It is merely necessary that the target material be irradiated until the desired amount of Mo activity is formed. A convenient amount is about 100-300 millicuries of Mo" per loaded column, or about 200-1000 millicuries per gram of irradiated M00 What is claimed is:
1. A process for producing radioactive technetium-99m which comprises the steps of:
(l) irradiating a base-soluble molybdenum containing material in a neutron flux until the desired amount of M0 activity is formed,
(2) dissolving the irradiated molybdenum containing material, containing the radioactive M0, in a base,
(3) adjusting the pH of the solution prepared in step (2) to be acidic and above pH 2.5,
(4) contacting an inorganic anion exchange material with the pH adjusted solution of step (3) thereby loading the molybdenum on the exchange material, and
(5) extracting technetium-99m, formed by the radioactive decay of M0 from the loaded anion exchange material with an acid.
2. The process of claim 1 wherein the inorganic anion exchange material is alumina.
3. The process of claim 2 wherein the base used to dissolve the irradiated material is ammonium hydroxide.
4. The process of claim 2 wherein the pH of the solution prepared in step (2) is adjusted to be within the range of 3.0 to 3.5.
5. The process of claim 2 wherein the particle size of the alumina is 100 to 200 mesh.
6. The process of claim 2 wherein the acid used for extracting the technetium-99m from the loaded alumina is hydrochloric acid.
7. A process for producing radioactive technetium-99m which comprises the steps of:
(1) irradiating M00 in a neutron flux until the desired amount of M0 activity is formed,
(2) dissolving the irradiated M00 containing radioactive Mo in ammonium hydroxide,
(3) adjusting the pH of the solution formed in step (2) to be acidic and above pH 2.5,
(4) contacting a column of alumina with the pH adjusted solution of step (3) thereby loading the alumina With molybdate ions, and
(5) eluting technetium-99m, formed by the radioactive decay of M0 from the loaded alumina column with hydrochloric acid.
8. The process of claim 7 wherein the pH of the solution formed in step (2) is adjusted to be within the range of 3.0 to 3.5.
9. A process for producing radioactive technetium-99m which comprises the steps of:
(1) providing a solution of ammonium molybdate in which at least some of the molybdenum is radioactive 99 (2) adjusting the pH of the solution to be acidic and above pH 2.5,
(3) contacting a column of alumina with the pH adjusted solution of step (2), thereby loading the column with molybdate ions, and
(4) eluting technetium-99m, formed by the radioactive decay of M0 from the loaded alumina column with an acid.
10. The process of claim 9 wherein the pH of the solution is adjusted to be within the range of 3.0 to 3.5.
11. The process of claim 9 wherein the acid used for eluting the loaded alumina column is hydrochloric acid.
12. A process for producing radioactive technetium- 99rn which comprises the steps of:
(1) providing a solution containing molybdate ions, which is acidic, has a pH above 2.5, and in which at least some of the molybdenum is radioactive M0 (2) loading a column of alumina with the solution of step 1) and (3) eluting technetium-99m, formed by the radioactive decay of M0 from the loaded alumina column with an acid.
13. The process of claim 12 wherein the pH of the solution is adjusted to be within the range of 3.0 to 3.5.
14. The process of claim 12 wherein the acid used for eluting the loaded alumina column is hydrochloric acid.
15. A process for producing a solution containing radioactive molybdenum-99, from which solution radioactive molybdenum-99 can be loaded onto an inorganic anion exchange material, which process comprises the steps of:
(l) irradiating M00 in a neutron flux until the desired amount of Mo activity is formed,
(2) dissolving the irradiated M00 containing radioactive Mo in a base, and
(3) adjusting the pH of the solution formed in step (2) to be acidic and above pH 2.5.
16. A process for producing a solution containing radioactive molybdenum-99, from which solution radioactive molybdenum-99 can be loaded onto alumina, which process comprises the steps of:
(l) irradiating M00 in a neutron flux until the desired amount of Mo activity is formed,
(2) dissolving the irradiated M00 containing radioactive M0 in ammonium hydroxide and,
(3) adjusting the pH of the solution prepared in step (2) to be within the range of 3.0 to 3.5.
17. A process for producing the combination comprising alumina having loaded thereon radioactive molybdenum-99 which process comprises the steps of:
(1) irradiating M00 in a neutron flux until the desired amount of Mo activity is formed,
(2) dissolving the irradiated M00 containing radioactive M0 in a base,
5 (3) adjusting the pH of the solution formed in step (2) to be acidic and above pH 2.5, and
(4) loading the pH adjusted solution of step (3) on a column of alumina.
18. A process for producing the combination comprising alumina having loaded thereon radioactive molybdenum-99 which process comprises the steps of (1) irradiating M00 in a neutron flux until the desired amount of M0 activity is formed,
(2) dissolving the irradiated MoO containing radioactive M0 in ammonium hydroxide,
(3) adjusting the pH of the solution prepared in step (2) to be within the range of 3.0 to 3.5, and
(4) loading the pH adjusted solution of step (3) on a column of alumina.
References Cited O 1 CARL D. QUARF'ORTH, Primary Examiner.
L. DEWAY'NE RUTLEDGE, Examiner.
H. E. BEHREND, Assistant Examiner.

Claims (1)

1. A PROCESS FOR PRODUCING RADIOACTIVE TECHNETIUM-99M WHICH COMPRISES THE STEPS OF: (1) IRRADIATING A BASE-SOLUBLE MOLYBDENUM CONTAINING MATERIAL IN A NEUTRON FLUX UNTIL THE DESIRED AMOUNT OF MO99 ACTIVITY IS FORMED, (2) DISSOLVING THE IRRADIATED MOLYBDENUM CONTAINING MATERIAL, CONTAINING THE RADIOACTIVE MO99, IN A BASE, (3) ADJUSTING THE PH OF THE SOLUTION PREPARED IN STEP (2) TO BE ACIDIC AND ABOVE PH 2.5, (4) CONTACTING AN INORGANIC ANION EXCHANGE MATERIAL WITH THE PH ADJUSTED SOLUTION OF STEP (3) THEREBY LOADING THE MOLYBDENUM ON THE EXCHANGE MATERIAL, AND (5) EXTRACTING TECHNETIUM-99M, FORMED BY THE RADIOACTIVE DECAY OF MO99, FROM THE LOADED ANION EXCHANGE MATERIAL WITH AN ACID.
US399842A 1964-09-28 1964-09-28 Production of high purity radioactive isotopes Expired - Lifetime US3382152A (en)

Priority Applications (6)

Application Number Priority Date Filing Date Title
US399842A US3382152A (en) 1964-09-28 1964-09-28 Production of high purity radioactive isotopes
GB25433/66A GB1131546A (en) 1964-09-28 1966-06-08 Production of high-purity radioactive isotopes
CH850866A CH454805A (en) 1964-09-28 1966-06-13 Process for preparing molybdenum-99
DE19661544156 DE1544156A1 (en) 1964-09-28 1966-06-18 Process for the production of high-purity radioactive isotopes
BE682978D BE682978A (en) 1964-09-28 1966-06-22
FR66641A FR1486542A (en) 1964-09-28 1966-06-23 Production of high purity radioactive isotopes

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
US399842A US3382152A (en) 1964-09-28 1964-09-28 Production of high purity radioactive isotopes
DE19661544156 DE1544156A1 (en) 1964-09-28 1966-06-18 Process for the production of high-purity radioactive isotopes

Publications (1)

Publication Number Publication Date
US3382152A true US3382152A (en) 1968-05-07

Family

ID=25752849

Family Applications (1)

Application Number Title Priority Date Filing Date
US399842A Expired - Lifetime US3382152A (en) 1964-09-28 1964-09-28 Production of high purity radioactive isotopes

Country Status (5)

Country Link
US (1) US3382152A (en)
BE (1) BE682978A (en)
CH (1) CH454805A (en)
DE (1) DE1544156A1 (en)
GB (1) GB1131546A (en)

Cited By (14)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3466361A (en) * 1968-04-18 1969-09-09 Atomic Energy Commission Technetium-99m labeled chelates
FR2161893A1 (en) * 1971-09-02 1973-07-13 Mallinckrodt Chemical Works
US3833469A (en) * 1971-08-31 1974-09-03 Atomic Energy Of Australia Process for the production of technetium-99m from neutron irradiated molybdenum trioxide
US4158700A (en) * 1976-03-08 1979-06-19 Karageozian Hampar L Method of producing radioactive technetium-99M
US4701308A (en) * 1984-12-28 1987-10-20 Commissariat A L'energie Atomique Process for the recovery of molybdenum-99 from an irradiated uranium alloy target
US20110206579A1 (en) * 2010-02-19 2011-08-25 Glenn Daniel E Method and apparatus for the extraction and processing of molybdenum-99
US20110272272A1 (en) * 2010-05-10 2011-11-10 Los Alamos National Security, Llc Method of producing molybdenum-99
US20110280357A1 (en) * 2010-05-14 2011-11-17 Stevenson Nigel R Tc-99m PRODUCED BY PROTON IRRADIATION OF A FLUID TARGET SYSTEM
US20120314828A1 (en) * 2010-02-01 2012-12-13 Arnd Baurichter METHOD AND DEVICE FOR PRODUCING 99mTc
JP2013035714A (en) * 2011-08-08 2013-02-21 Japan Atomic Energy Agency Method for producing technetium-99m solution having high concentration and high radioactivity
US8569713B2 (en) 2009-05-13 2013-10-29 Lantheus Medical Imaging, Inc. Radionuclide generator and method of sterilization
US20140234186A1 (en) * 2010-10-07 2014-08-21 Luis A.M.M. Barbosa Extraction Process
US9793023B2 (en) 2013-09-26 2017-10-17 Los Alamos National Security, Llc Recovery of uranium from an irradiated solid target after removal of molybdenum-99 produced from the irradiated target
US9842664B2 (en) 2013-09-26 2017-12-12 Los Alamos National Security, Llc Recovering and recycling uranium used for production of molybdenum-99

Families Citing this family (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
NL7008953A (en) * 1969-06-20 1970-12-22
NL165321C (en) * 1971-03-02 1981-03-16 Byk Mallinckrodt Cil Bv METHOD FOR THE MANUFACTURE OF A RADIO ISOTOPE GENERATOR GENERATOR.
DE2610948C3 (en) * 1976-03-16 1980-01-10 Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe Process for the extraction of molybdenum -99 from a matrix containing fissile substances and fission products irradiated with neutrons
DE2610947C3 (en) * 1976-03-16 1980-01-10 Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe Process for the extraction of molybdenum-99 from a matrix containing fissile substances and fission products irradiated with neutrons
US4280053A (en) * 1977-06-10 1981-07-21 Australian Atomic Energy Commission Technetium-99m generators
US11286172B2 (en) * 2017-02-24 2022-03-29 BWXT Isotope Technology Group, Inc. Metal-molybdate and method for making the same

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
None *

Cited By (20)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3466361A (en) * 1968-04-18 1969-09-09 Atomic Energy Commission Technetium-99m labeled chelates
US3833469A (en) * 1971-08-31 1974-09-03 Atomic Energy Of Australia Process for the production of technetium-99m from neutron irradiated molybdenum trioxide
FR2161893A1 (en) * 1971-09-02 1973-07-13 Mallinckrodt Chemical Works
US4158700A (en) * 1976-03-08 1979-06-19 Karageozian Hampar L Method of producing radioactive technetium-99M
US4701308A (en) * 1984-12-28 1987-10-20 Commissariat A L'energie Atomique Process for the recovery of molybdenum-99 from an irradiated uranium alloy target
US8822950B2 (en) 2009-05-13 2014-09-02 Lantheus Medical Imaging, Inc. Radionuclide generator and method of sterilization
US8569713B2 (en) 2009-05-13 2013-10-29 Lantheus Medical Imaging, Inc. Radionuclide generator and method of sterilization
US9576692B2 (en) * 2010-02-01 2017-02-21 Siemens Aktiengesellschaft Method and device for producing 99mTc
US20120314828A1 (en) * 2010-02-01 2012-12-13 Arnd Baurichter METHOD AND DEVICE FOR PRODUCING 99mTc
US8449850B2 (en) * 2010-02-19 2013-05-28 Babcock & Wilcox Technical Services Group, Inc. Method and apparatus for the extraction and processing of molybdenum-99
US20110206579A1 (en) * 2010-02-19 2011-08-25 Glenn Daniel E Method and apparatus for the extraction and processing of molybdenum-99
US8450629B2 (en) * 2010-05-10 2013-05-28 Los Alamos National Security, Llc Method of producing molybdenum-99
US20110272272A1 (en) * 2010-05-10 2011-11-10 Los Alamos National Security, Llc Method of producing molybdenum-99
US20110280357A1 (en) * 2010-05-14 2011-11-17 Stevenson Nigel R Tc-99m PRODUCED BY PROTON IRRADIATION OF A FLUID TARGET SYSTEM
US9336916B2 (en) * 2010-05-14 2016-05-10 Tcnet, Llc Tc-99m produced by proton irradiation of a fluid target system
US20140234186A1 (en) * 2010-10-07 2014-08-21 Luis A.M.M. Barbosa Extraction Process
US9991012B2 (en) * 2010-10-07 2018-06-05 Mallinckrodt Nuclear Medicine Llc Extraction process
JP2013035714A (en) * 2011-08-08 2013-02-21 Japan Atomic Energy Agency Method for producing technetium-99m solution having high concentration and high radioactivity
US9793023B2 (en) 2013-09-26 2017-10-17 Los Alamos National Security, Llc Recovery of uranium from an irradiated solid target after removal of molybdenum-99 produced from the irradiated target
US9842664B2 (en) 2013-09-26 2017-12-12 Los Alamos National Security, Llc Recovering and recycling uranium used for production of molybdenum-99

Also Published As

Publication number Publication date
GB1131546A (en) 1968-10-23
DE1544156A1 (en) 1970-06-04
CH454805A (en) 1968-04-30
BE682978A (en) 1966-12-22

Similar Documents

Publication Publication Date Title
US3382152A (en) Production of high purity radioactive isotopes
Spedding et al. The separation of rare earths by ion exchange. 1, 2 I. cerium and yttrium
US4859431A (en) Rhenium generator system and its preparation and use
JPS628760B2 (en)
US3322509A (en) Method of reprocessing and/or separating nuclear fuels
US4094953A (en) Process for recovering molybdenum-99 from a matrix containing neutron irradiated fissionable materials and fission products
WO2010146722A1 (en) Method and system for concentrating radioactive technetium as raw material for radioactive drug and labeling compound therefor and collecting the same by elution
US3468808A (en) Production of high purity radioactive technetium-99m
WO2013010047A1 (en) Process for producing tc-99m
US3694369A (en) Selective ion exchange for the isolation of certain alkaline earths
Mushtaq Inorganic ion-exchangers: their role in chromatographic radionuclide generators for the decade 1993–2002
Sameh Production Cycle for Large Scale Fission Mo‐99 Separation by the Processing of Irradiated LEU Uranium Silicide Fuel Element Targets
Lewis Production of high specific activity molybdenum-99 for preparation of technetium-99m generators
US2877093A (en) Adsorption method for separating metal cations
Adar et al. Ion-exchange behaviour of the transuranium elements in LiNO3 solutions
US2767044A (en) Plutonium recovery process
US3519385A (en) Method for separating molybdenum from technetium
GB1473683A (en) Process for the preparation of molybdenum-99
US2887358A (en) Large scale method for the production and purification of curium
US4093697A (en) Process for recovering molybdenum-99 from a matrix containing neutron irradiated fissionable materials and fission products
US2942943A (en) Process for separating iodine-132 from fission products
Jenkins Ion exchange in the atomic energy industry with particular reference to actinide and fission product separations—a review
Travesi et al. Neutron activation analysis of microgram amounts of thorium in uranium ores and process liquors by means of thorium-233
US3065044A (en) Recovery of aluminum from fission products
Bernhard Separation of radionuclides from a fission product solution by ion exchange on alumina