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WO2025234135A1 - Procédé d'extraction de technétium 99m à partir de molybdène 99 à faible activité spécifique, procédé de production d'une solution saline physiologique contenant du technetium 99m à l'aide de ce procédé, et système de récupération de technetium 99m à partir de molybdène naturel - Google Patents

Procédé d'extraction de technétium 99m à partir de molybdène 99 à faible activité spécifique, procédé de production d'une solution saline physiologique contenant du technetium 99m à l'aide de ce procédé, et système de récupération de technetium 99m à partir de molybdène naturel

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Publication number
WO2025234135A1
WO2025234135A1 PCT/JP2024/022706 JP2024022706W WO2025234135A1 WO 2025234135 A1 WO2025234135 A1 WO 2025234135A1 JP 2024022706 W JP2024022706 W JP 2024022706W WO 2025234135 A1 WO2025234135 A1 WO 2025234135A1
Authority
WO
WIPO (PCT)
Prior art keywords
technetium
molybdenum
solution
column
activated carbon
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.)
Pending
Application number
PCT/JP2024/022706
Other languages
English (en)
Japanese (ja)
Inventor
克嘉 蓼沼
エドワード マウゾルフ
エリック ブイ ジョンストン
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.)
Chemical Design Labo
Chemical Design Labo LLC
Innovative Fuel Solutions LLC
Original Assignee
Chemical Design Labo
Chemical Design Labo LLC
Innovative Fuel Solutions LLC
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 Chemical Design Labo, Chemical Design Labo LLC, Innovative Fuel Solutions LLC filed Critical Chemical Design Labo
Priority to US18/858,182 priority Critical patent/US12400770B1/en
Priority to PCT/JP2024/032521 priority patent/WO2025234140A1/fr
Priority to JP2025502921A priority patent/JP7696148B1/ja
Publication of WO2025234135A1 publication Critical patent/WO2025234135A1/fr
Pending legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21G—CONVERSION OF CHEMICAL ELEMENTS; RADIOACTIVE SOURCES
    • G21G4/00—Radioactive sources
    • G21G4/04—Radioactive sources other than neutron sources
    • G21G4/06—Radioactive sources other than neutron sources characterised by constructional features
    • G21G4/08—Radioactive sources other than neutron sources characterised by constructional features specially adapted for medical application
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02P—CLIMATE CHANGE MITIGATION TECHNOLOGIES IN THE PRODUCTION OR PROCESSING OF GOODS
    • Y02P10/00—Technologies related to metal processing
    • Y02P10/20—Recycling

Definitions

  • Patent Document 2 like Patent Document 1, compares and studies two methods: a method of recovering 99m Tc, the daughter nuclide of 99 Mo produced by 98 Mo(n, ⁇ ) reaction by irradiating natural isotope Mo as a raw material with neutrons in a nuclear reactor, using spherical activated carbon (BAC) to recover 99m Tc, the daughter nuclide of 99 Mo; and a method of passing a Mo solution containing 99 Mo through an AC column by a pressurized flow in which it is forced into the AC column with a pump, or a reduced pressure flow in which it is sucked in with a pump.
  • BAC spherical activated carbon
  • Patent Document 3 like Patent Documents 1 and 2, describes a method for recovering 99m Tc, a daughter nuclide, from 99 Mo produced by the 98 Mo(n, ⁇ ) reaction produced by irradiating natural isotope Mo in a nuclear reactor with neutrons , by using AC.
  • the method mainly involves piping a Mo solution tank containing 99 Mo, which is installed inside a double-walled cell to shield radiation such as ⁇ rays emitted from 99 Mo and prevent leakage of radioactive materials, to an external cell in which an AC column with low radiation shielding ability is installed, and piping the Mo solution to the AC column installed in the external cell and circulating it back to the internal Mo solution tank, thereby selectively adsorbing and collecting 99m Tc to prevent radiation leakage to the outside.
  • the present invention describes a method and an apparatus for purifying a 99m Tc recovery solution by removing Mo, 99 Mo, radioactive impurities and other impurities contained in the 99m Tc recovery solution by passing the solution through a column filled with AL placed after an AC column.
  • the amount of Mo ( 99 Mo) solution is, for example, 5 to 20 L, it will take 2 to 5 hours or more to pass the solution through the AC column to adsorb and collect 99m Tc, reducing work efficiency and posing the risk that the recovered 99m Tc, which has a short half-life, will deteriorate to 99g Tc, making it unusable as a pharmaceutical raw material.
  • 99g Tc (technetium 99grand) is one of the radioactive isotopes of Tc with a half-life of 211,100 years that is produced from 99m Tc, and is produced in proportion to the time that has elapsed since the extraction and separation of the pharmaceutical raw material 99m Tc , and if there is too much, it will become an impurity in the pharmaceutical raw material 99m Tc.
  • an AC capable of selectively adsorbing and recovering a trace amount of 99m Tc even when the atomic ratio of Mo ( 99 Mo) is 10 16 or more may be used.
  • the present invention therefore aims to provide a method for extracting technetium-99m from low-specific activity molybdenum-99 in a short period of time, without being affected by the amount of molybdenum solution.
  • the method of the present invention for recovering technetium-99m from low specific activity molybdenum-99 is a method for recovering technetium-99m, a daughter nuclide produced by the decay of molybdenum-99 contained in a high-concentration molybdenum solution containing molybdenum-99 with low specific activity, by separating and recovering the technetium-99m with activated carbon, the daughter nuclide being produced by the decay of molybdenum-99.
  • the activated carbon is immersed in the molybdenum solution and selectively adsorbs trace amounts of technetium-99m even when the molybdenum atom number ratio is 10 or more .
  • the molybdenum solution contains the radionuclide molybdenum-99 produced by the neutron capture (n, gamma) reaction of the natural isotope of molybdenum.
  • the activated carbon is packed into a cylindrical metal mesh container that is not a column with a restricted flow rate, and is immersed in the molybdenum solution that is being stirred and flowing.
  • the present invention provides a method for producing a physiological saline solution containing technetium-99m, which comprises washing with water the molybdenum remaining in the pores of activated carbon to which technetium-99m recovered by the method for recovering technetium-99m from low specific activity molybdenum-99 has been adsorbed; eluting the solution containing technetium-99m from the activated carbon with an alkaline solution, passing the solution through an IER column packed with a strongly acidic cation exchange resin to remove the alkaline components; further passing the solution through an AL column packed with alumina to capture the technetium-99m; and eluting the technetium-99m from the alumina column using physiological saline, thereby purifying the solution into a physiological saline solution containing technetium-99m from which impurities have been removed.
  • the container containing the activated carbon, the IER column, and the AL column are made of materials that can be sterilized in an autoclave.
  • the system for recovering technetium-99m from natural molybdenum of the present invention comprises: a means for producing a high-concentration molybdenum solution containing molybdenum-99 with low specific activity, which is produced by the neutron capture (n, gamma) reaction of the natural isotope of molybdenum; a means for producing the daughter nuclide technetium-99m in the molybdenum solution by the decay of molybdenum-99; and a means for filling a cylindrical metal mesh vessel, which is not a column with a restricted flow rate, with activated carbon and immersing the activated carbon in the molybdenum solution, which is being stirred and flowing.
  • the method is characterized by comprising: a means for washing the remaining molybdenum-99 from the activated carbon on which technetium-99m has been adsorbed; a means for eluting technetium-99m from the washed activated carbon using an alkaline solution, passing the solution through a strongly acidic cation exchange resin column to remove the alkaline components, and passing the resulting solution through an alumina column to capture the technetium-99m; and a means for eluting technetium-99m from the alumina column using physiological saline and recovering purified technetium-99m.
  • a high-concentration Mo solution containing radioactive 99 Mo is produced and left for about 24 hours, whereby 99m Tc is produced from 99 Mo and mixed in a state of radioactive equilibrium (the ratio of the radioactivity of the parent nuclide to that of the daughter nuclide is constantly balanced).
  • a state of radioactive equilibrium the ratio of the radioactivity of the parent nuclide to that of the daughter nuclide is constantly balanced.
  • the target amount of 99m Tc is selectively adsorbed and collected by AC during the time it takes for 99m Tc to be produced from 99 Mo and reach radioactive equilibrium or the time the desired amount of 99m Tc is produced, and this method is particularly effective for recovering 99m Tc with a short half-life (6 hours).
  • FIG. 1 is a diagram showing an outline of a method for extracting technetium-99m from low specific activity molybdenum-99 according to the present invention, a method for producing a physiological saline solution containing technetium-99m using the method, and a system for recovering technetium-99m from natural molybdenum.
  • FIG. 1 is a diagram showing a conventional method for passing a molybdenum solution through an activated carbon column.
  • FIG. 1 is a diagram showing the configuration of a method for extracting technetium-99m from low specific activity molybdenum-99 according to the present invention, a method for producing a physiological saline solution containing technetium-99m using the method, and a system for recovering technetium-99m from natural molybdenum.
  • 1 is a diagram comparing the process of the present invention for extracting technetium-99m from low specific activity molybdenum-99 with the process of a conventional method.
  • FIG. 1 is a diagram showing process conditions for short-time production of a physiological saline solution containing technetium-99m according to the present invention.
  • a cylindrical metal (e.g., stainless steel) mesh container filled with AC is constantly immersed in a 99 Mo solution tank, and the Mo solution in which the AC container is immersed is stirred and flowed, so that the AC is always in a state where it can adsorb 99m Tc.
  • the AC container is removed from the Mo solution, and the non-AC-adsorbed 99Mo remaining in the AC pores is washed away with water. Then, the AC with 99mTc adsorbed thereto is treated with an alkaline solution to elute the 99mTc captured by the AC.
  • the solution is purified with a strongly acidic cation exchange resin (IER) and alumina (AL) to recover high-purity 99mTc .
  • IER strongly acidic cation exchange resin
  • AL alumina
  • 99mTc is the radionuclide technetium-99m
  • 99Mo is the radionuclide molybdenum-99.
  • 99Mo is the parent nuclide
  • 99mTc is the daughter nuclide.
  • AC is activated carbon
  • IER is ion exchange resin
  • AL is alumina (aluminum oxide).
  • 1 and 3 show a method for extracting technetium-99m from low-specific activity molybdenum-99, a method for producing a physiological saline solution containing technetium-99m using the method, and a system for recovering technetium-99m from natural molybdenum.
  • a Mo solution containing 99Mo instead of passing a Mo solution containing 99Mo through an AC column, 99mTc in the Mo solution is adsorbed and collected in an AC-filled cylindrical metal mesh vessel, and 99mTc is purified and recovered.
  • Figure 2 shows a conventional method of passing a molybdenum solution through an activated carbon column.
  • Figure 4 shows a comparison of the method of extracting technetium-99m from low-specific activity molybdenum-99 according to the present invention with the conventional process.
  • Figure 5 shows the process conditions for short-time production of a physiological saline solution containing technetium-99m.
  • the method for extracting technetium-99m from low-specific activity molybdenum-99 involves using activated carbon to separate and recover the daughter nuclide technetium-99m produced by the decay of molybdenum-99 contained in a high-concentration molybdenum solution containing molybdenum-99 with low specific activity.
  • the activated carbon is packed in a cylindrical metal mesh container, not a column with a limited flow rate, and immersed in a stirred, flowing molybdenum solution, selectively adsorbing trace amounts of technetium-99m even when the molybdenum atom number ratio is 10 16 or more.
  • the molybdenum solution contains the radionuclide molybdenum-99, which is produced by the neutron capture (n, ⁇ ) reaction of the natural isotope molybdenum.
  • the method for producing a physiological saline solution containing technetium-99m involves washing with water the molybdenum remaining in the pores of activated carbon to which technetium-99m recovered in the method for recovering technetium-99m from low specific activity molybdenum-99 has been adsorbed, eluting the solution containing technetium-99m from the activated carbon with an alkaline solution, passing the solution through an IER column packed with a strongly acidic cation exchange resin to remove the alkaline components, and then passing the solution through an AL column packed with alumina to capture the technetium-99m.
  • Technetium-99m is then eluted from the alumina column using physiological saline, resulting in a purified physiological saline solution containing technetium-99m from which impurities have been removed.
  • the system for recovering technetium-99m from natural molybdenum includes: a means for producing a high-concentration molybdenum solution containing molybdenum-99 with low specific activity, produced by the neutron capture (n, gamma) reaction of the natural isotope of molybdenum; a means for producing the daughter nuclide technetium-99m in the molybdenum solution by the decay of molybdenum-99; a means for filling a cylindrical metal mesh container (not a column with a restricted flow rate) with activated carbon and immersing the activated carbon in a stirred, flowing molybdenum solution; a means for washing the remaining molybdenum-99 from the activated carbon with adsorbed technetium-99m; a means for eluting technetium-99m from the washed activated carbon with an alkaline solution, passing the solution through a strong acidic cation exchange resin column to remove the alkaline components, and passing the resulting solution through
  • a tank 100 containing Mo solution is placed in a hot cell that is shielded from radiation due to the high radiation dose of 99 Mo.
  • the Mo solution tank 100 is equipped with a stirrer 110 for stirring the solution, and also with a support 130 for holding a metal mesh cylindrical container 120 containing AC in the solution. Multiple tanks 100 may be placed in the hot cell.
  • a Na299MoO4 solution containing the radionuclide 99Mo is supplied to a tank 100.
  • 99Mo is produced by irradiating the natural isotope MoO3 with neutrons in a nuclear reactor in advance. Dissolving MoO3 containing 99Mo in an alkaline (NaOH) solution results in a pH - neutral Na299MoO4 solution .
  • the Mo solution containing radioactive 99Mo is, for example, a high-concentration Mo solution containing 500 g of Mo (750 g as MoO3 ) in 2 L.
  • a high-concentration Mo solution containing 500 g of Mo in 2 L is required, but a high-concentration Mo solution containing 50 g of Mo (75 g as MoO3 ) in 200 mL, which is one-tenth of that amount, or a high-concentration, large-volume Mo solution containing 5 kg of Mo (7.5 kg as MoO3 ) in 20 L, which is ten times the amount, may also be used.
  • a metal mesh cylindrical container 120 containing AC is placed in a tank 100 containing a Mo solution containing 99 Mo, and the container is held in the Mo solution by a support 130.
  • the Mo solution is stirred using a stirrer 110 or the water flow of a circulating pump. By maintaining this state, 99m Tc produced in the Mo solution is adsorbed and collected by the AC.
  • the metal mesh cylindrical container 120 may be pulled out of the Mo solution after waiting for this time to elapse, or may be pulled out at any time before reaching radioactive equilibrium.
  • 99m Tc can be adsorbed by AC during the period from when the metal mesh cylindrical container 120 is immersed in the Mo solution until it is pulled out.
  • conventional TcMM (Technetium-99m Master Milker) uses a method in which the entire amount of Mo solution is passed through an AC column to adsorb 99m Tc in the Mo solution onto the AC.
  • the AC column is a cylindrical container filled with AC, and the liquid comes into contact with the AC as it passes through the cylinder from the inlet to the outlet.
  • the flow rate of the Mo solution passing through the AC column is limited, which limits the AC column's ability to process the Mo solution, making it problematic as a recovery technology for 99m Tc, which has a short half-life (lifetime).
  • the system for highly concentrating, purifying, and recovering 99mTc from a low specific activity Mo solution is installed in a hot cell 140 isolated by a thick shielding wall to shield against high radiation.
  • Activated 99MoO3 is dissolved in alkali to produce a 99MoO3 solution in advance.
  • the 99MoO3 solution is supplied to a plurality of storage tanks 100 with a capacity of 1 to 20 L provided in the hot cell 140 , and a highly concentrated Mo solution with a 99Mo radioactivity of 500 Ci is stored.
  • the metallic mesh cylindrical container 120 containing the AC is placed in the tank 100 using a hook, a carrier, or the like, and is held in the Mo solution containing 99 Mo by a support 130.
  • the radioactive 99 Mo decays and changes to 99m Tc, forming a Mo solution containing 99m Tc.
  • the metal mesh cylindrical container 120 has been immersed in the Mo solution, it is advisable to stir the Mo solution with a stirrer 110 to bring the Mo solution into efficient contact with the AC.
  • 99m Tc produced in the Mo solution is adsorbed and collected by the AC.
  • the metal mesh cylindrical container 120 is then lifted out of the tank 100, and the AC with 99m Tc adsorbed thereon is recovered.
  • the AC is then placed in a column and washed with water to remove any remaining non-adsorbed 99 Mo and other impurities from the AC.
  • An alkaline (NaOH) solution is supplied to the AC-containing column while adjusting the flow rate and temperature, and the solution is passed through.
  • 99m Tc is eluted from the AC into the alkaline solution, and the discharged alkaline solution containing 99m Tc is passed through the IER column 150.
  • the alkaline component is captured by a strongly acidic cation exchange resin, and the discharged solution containing 99m Tc is passed through the AL column 160.
  • the radioactivity attached thereto can be naturally attenuated to a low level, and then solidified, etc.
  • a space for storing and accommodating various radioactive and non-radioactive wastes generated in the process may be provided in the hot cell 140, etc.
  • the containers containing the AC metal mesh cylindrical container 120, AC containing column for rinsing the AC with water
  • IER column 150, and AL column 160 are preferably made of materials and have contents (AC, IER, AL) that can be sterilized in an autoclave (121°C, 2 atmospheres).
  • the conventional process is a flow-type TcMM in which 99m Tc contained in a Mo solution is adsorbed and collected by passing the solution through an AC column.
  • the present invention is an improved batch-type TcMM in which, instead of passing the Mo solution through an AC column, a cylindrical metal mesh container 120 containing an AC is immersed in a flowing high-concentration Mo solution, so that 99m Tc produced in the Mo solution is adsorbed by the AC.
  • the concentration of 99m Tc becomes even lower, so when 99m Tc is adsorbed and collected on an AC column, a larger amount of Mo solution must be passed through the AC column. For example, if the amount of Mo solution is 5 to 20 L, it will take 2 to 5 hours or more to pass the solution through the AC column, and the recovered 99m Tc may be altered to 99 g Tc, making it unusable as a pharmaceutical raw material.
  • the present invention even if the AC contained in the metal mesh cylindrical container 120 contains 99mTc , which is a daughter nuclide produced by decay of 99Mo in a high-concentration Mo solution containing radioactive 99Mo, in an atomic ratio of 10 to 16 , it is possible to selectively separate and recover a trace amount of 99mTc .
  • the metal mesh cylindrical container 120 containing AC is immersed in the Mo solution, and the Mo solution is stirred and flows around the metal mesh cylindrical container 120, thereby facilitating adsorption of 99m Tc in the Mo solution by the AC. There is no need to adjust the flow rate of the Mo solution to pass it through the AC column, and 99m Tc is always adsorbed by the AC from the entire Mo solution present around the metal mesh cylindrical container 120, making it possible to collect 99m Tc in a short time.
  • a cylindrical metal mesh container 120 containing AC is immersed in a Mo solution, and the time required for each step of recovering purified 99m Tc as a pharmaceutical raw material from the AC that has adsorbed and collected 99m Tc is significantly shorter than that of conventional methods. Since the AC constantly adsorbs and collects 99m Tc regardless of the amount of Mo solution or the radioactivity of 99 Mo, the process time required is zero. Thereafter, it takes about 10 minutes to purify and recover 99m Tc from the AC, and since the process can be operated in a constant time and the same way, this is an ideal method for manufacturing pharmaceutical raw materials that require strict quality and shipping arrangements.
  • MoO 3 (3,750 g) containing a very large amount of Mo (2,500 g) was dissolved in 6 M (molarity mol/L) NaOH (1.75-1.8 L), and then H 2 O was added to prepare a Mo solution (10 L) with a pH of 8-9.
  • the Mo solution was placed in a 15 L beaker, and 0.1 mg of Re (rhenium) was added as a substitute for 99m Tc (500 Ci).
  • a stainless steel cylindrical metal container (diameter 1.6 cm, length 6 cm, capacity 12 cc) filled with AC (4.5 g) was immersed in the Mo solution, and the rotor blades of the stirrer were rotated (30 rpm) in the Mo solution for 6 hours.
  • the metal mesh cylindrical container was removed from the Mo container and washed with water to remove any unadsorbed Mo remaining in the pores of the AC.
  • the Re adsorbed on the AC was then eluted with 1.3 M NaOH (30 mL).
  • the solution was passed through an IER column packed with a strongly acidic cation exchange resin, and then through an AL column containing activated alumina (6 g), where the Re was adsorbed and captured by the alumina. 20 mL of saline (0.9% NaCl) was passed through the AL column to which the Re had been adsorbed, and a saline solution (pH 4.8-5.2) containing Re was recovered.
  • the half-life of 99 Mo was 65.94 hours, and the half-life of 99m Tc was 6.01 hours.
  • the amount of 99 Mo (500 Ci) was 1.04 mg, which is 1/500,000 relative to Mo (500 g), and the amount of 99m Tc (500 Ci) was 0.095 mg, which is 1/5,000,000 relative to Mo (500 g).
  • the radioactivity of 99 Mo was less than 5 ⁇ 10 4 Bq (Becquerels), with a weight ratio to Mo (500 g) of less than 6e -15 .
  • the radioactivity of 99m Tc was less than 6 ⁇ 10 4 Bq (Becquerels), with a weight ratio to Mo (500 g) of less than 6e -16 .
  • the amount of Re recovered was 0.092-0.096 mg, and the recovery rate of Re was approximately 94%. Since this was Re equivalent to 99m Tc (500 Ci), it is believed that similar results would be obtained when a metal mesh cylindrical container filled with AC was immersed in a Mo solution and 99m Tc was adsorbed and collected with AC. This result indicates that even when the ratio of the number of 99 Mo atoms to the daughter nuclide 99m Tc produced by the decay of 99 Mo is 10 16 or more in a high-concentration Mo solution, AC selectively adsorbs trace amounts of 99m Tc in the solution.
  • a high-concentration Mo solution containing radioactive 99 Mo is produced and left for about 24 hours, whereby 99m Tc is produced from 99 Mo and mixed in a state of radioactive equilibrium (the ratio of the radioactivity of the parent nuclide to that of the daughter nuclide is constantly balanced).
  • a state of radioactive equilibrium the ratio of the radioactivity of the parent nuclide to that of the daughter nuclide is constantly balanced.
  • the target amount of 99m Tc is selectively adsorbed and collected by AC during the time it takes for 99m Tc to be produced from 99 Mo and reach radioactive equilibrium or the time the desired amount of 99m Tc is produced, and this method is particularly effective for recovering 99m Tc with a short half-life (6 hours).

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  • Chemical Kinetics & Catalysis (AREA)
  • General Chemical & Material Sciences (AREA)
  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
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Abstract

La présente invention extrait du technétium 99m à partir de molybdène 99 à faible activité spécifique en un court laps de temps sans être affectée par la quantité de solution de molybdène.　Ce procédé de récupération de technétium 99m à partir de molybdène 99 à faible activité spécifique comprend la séparation et la récupération du nucléide fils technétium 99m généré par la désintégration du molybdène 99 contenu dans une solution de molybdène à haute concentration contenant du molybdène 99 à faible activité spécifique à l'aide de charbon actif, et est caractérisé en ce que le charbon actif est immergé dans la solution de molybdène, et même si le rapport du nombre d'atomes de molybdène 99 est supérieur ou égal à 1016, la quantité infime de technétium 99m contenue dans celle-ci est adsorbée de manière sélective.
PCT/JP2024/022706 2024-05-07 2024-06-24 Procédé d'extraction de technétium 99m à partir de molybdène 99 à faible activité spécifique, procédé de production d'une solution saline physiologique contenant du technetium 99m à l'aide de ce procédé, et système de récupération de technetium 99m à partir de molybdène naturel Pending WO2025234135A1 (fr)

Priority Applications (3)

Application Number Priority Date Filing Date Title
US18/858,182 US12400770B1 (en) 2024-05-07 2024-06-24 Method for extracting technetium-99m from low specific activity molybdenum-99, method for producing physiological saline solution containing technetium-99m using extraction method thereof, and system for recovering technetium-99m from natural molybdenum
PCT/JP2024/032521 WO2025234140A1 (fr) 2024-05-07 2024-09-11 Procédé de purification/récupération de technetium 99m à usage médical à partir de molybdène 99 à faible activité spécifique, et système de purification/récupération de technetium 99m à usage médical à partir de molybdène 99 à faible activité spécifique
JP2025502921A JP7696148B1 (ja) 2024-06-24 2024-09-11 低比放射能モリブデン９９からの医療用テクネチウム９９ｍの精製回収方法、及び低比放射能モリブデン９９からの医療用テクネチウム９９ｍの精製回収システム

Applications Claiming Priority (2)

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JP2024-075307 2024-05-07
JP2024075307A JP7515815B1 (ja) 2024-05-07 2024-05-07 低比放射能モリブデン９９からのテクネチウム９９ｍの抽出方法、その方法を用いたテクネチウム９９ｍを含む生理的食塩水溶液の生成方法、及び天然モリブデンからのテクネチウム９９ｍの回収システム

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Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2011002370A (ja) * 2009-06-19 2011-01-06 Kaken:Kk 放射性医薬品およびその標識化合物原料としての放射性テクネチウムの濃縮および溶出回収方法、およびシステム

Patent Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2011002370A (ja) * 2009-06-19 2011-01-06 Kaken:Kk 放射性医薬品およびその標識化合物原料としての放射性テクネチウムの濃縮および溶出回収方法、およびシステム

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