Patent Application
20170229202
The invention relates to radioisotope production, and more particularly to apparatuses and methods for separation and isolation of clinical scale Technetium-99m (Tc-99m) from Molybdenum-99 (Mo-99) and other metals after the production of Tc-99m from molybdenum targets by cyclotrons.
Radioactive isotopes are widely used in medicine for diagnostic procedures. The most prominent of these radioisotopes is Molybdenum-99 (Mo-99), which is used as a precursor for producing Tc-99m. The Technetium-99m (Tc-99m) isotope is used in more than 80% of nuclear imaging tests for detecting cancer, heart disease and other medical conditions. Each day, hospitals and clinics around the world typically use Mo-99/Tc-99m in over 60,000 diagnostic procedures.
Technetium-99m (“Tc-99m” or 99mTc) is the daughter isotope of 99Mo produced by fission in a nuclear reactor. Due to the ongoing supply disruption of 99Mo from aging and soon to be shut down nuclear reactors, alternative production technologies have been developed for the production of 99mTc. The cyclotron technology typically involves the irradiation of enriched molybdenum target material (100Mo) with protons to produce a 99mTc via a (p, 2n) reaction. After irradiation, the target material must be chemically processed in order to separate the 99mTc as a radiochemical compound for clinical applications.
Various initial studies performed to assess the chemical composition of the proton irradiated target have shown the presence of Niobium (Nb). Molybdenum (Mo) and Technetium (Tc) isotopes. In order to provide a pharmaceutical grade radiochemical compound, a reliable separation technology and process is typically desired. In the early studies of the cyclotron production and separation of 99mTc, the post-irradiation separation process has been performed on laboratory scale units based on the Aqueous Biphasic Extraction Chromatography (ABEC) method. The ABEC method was developed for Technetium-99 oxides removal from nuclear waste. The technology requires dissolving the irradiated target and converting the obtained peroxo-molybdates and pertechnetates into ammonium molybdate and ammonium pertechnetate solution. The solution is then loaded into a small ABEC cartridge and, after multiple washings, the pertechnetate is eluted with water as sodium pertechnetate in a water solution. The radiopharmaceutical formulation typically requires an additional step of adding a saline solution. For low-scale production of 99mTc by a cyclotron (milligram quantities of target material), the ABEC technology typically provides relatively high separation efficiencies.
Alternatively, physical separation has been considered for Mo/Tc separation. For example, U.S. Pat. No. 5,802,439 assigned to Bennett et al. developed a Mo/Tc thermal generator, a so-called “Mo goat”, for Mo/Tc separation in the production of 99mTc based on linear accelerator technology. Linear accelerators are typically used to produce 99Mo via a 100Mo(γ,n)99Mo reaction in a linear accelerator. The obtained 99Mo is oxidized with nitric acid (HNO3) and loaded into a cavity of a thermal separation system, which is milked regularly and 99mTc is eluted as pertechnetate. After 5 days of elution, the system is transported for refill to the generator producer. The technology described by Bennett in U.S. Pat. No. 5,802,438 appears to provide a feasible solution for low specific activity produced 99Mo. For example, a small scale system for a Mo/Tc separation method describing a three components quartz sublimator for production of 94mTc has been reported previously in the literature. The irradiated target is introduced on the bottom part of a quartz tube system and heated up to 1100 degrees Centigrade (° C.). The formed molybdenum oxides are recovered as crystals in the middle part of the sublimation system while 94mTc is washed from the inner vertical quartz tube. This system and method can be used relatively successfully for manual separation when small radioactivity doses are handled.
In addition, a thermal separation for processing proton irradiated Mo is presented in International Patent Application Publication No. WO 2011/092174 A1. It is disclosed that the irradiated target material is heated over 400° C. in an oxygen atmosphere. If conducted at temperatures below 560° C. for the thermal oxidation of Tc to Technetium heptoxide (Tc2O7), the oxidation process maybe incomplete leading to the formation of lower oxidation state 99mTc compounds. Thus, the radiochemical purity of collected product can be altered or the process can occur with poor separation efficiency. The WO 2011/092174 A1 publication describes a method for the direct oxidation of the irradiated target. Also, the oxidation process as described therein appears not be applicable when the target material is deposited on a copper support because of the competitive oxidation process between copper and other components of the target.
Therefore, there is a need for an efficient automated method and system to overcome the aforementioned drawbacks. It is therefore desirable to provide an automated apparatus and method for the routine production of a highly pure sodium pertechnetate (Na99mTcO4) from a molybdenum target for rapid use in nuclear medicine centers.
Thus, a method, apparatus and system for metallic isotope separation by a combined thermal-vacuum distillation process addressing the aforementioned problems is desired.
Embodiments of methods, apparatuses and systems relate to an automated system and to methods to separate Tc from a Copper/Molybdenum/Technetium ternary system based on a combined vacuum evaporation and thermal distillation process.
In an embodiment, an improved process for the separation of 99mTC from molybdenum targets is described. The method for separation of 99mTc isotope from molybdenum targets includes: i) providing an initial multicomponent mixture of elements, the mixture containing 99mTc; ii) dissolving the multicomponent mixture of elements in an oxidizing agent to oxidize the mixture of elements; iii) heating the mixture of elements at a temperature sufficiently high enough to sublimate the mixture and generate a vaporized compound containing 99mTc; iv) condensing the vaporized compound containing 99mTc to form a reaction product; v) adding a base to the condensed reaction product to dissolve the 99mTc containing reaction product, such as an anhydride of pertechnic acid 99mTc, to form a salt of an acid containing 99mTc, such as a salt of 99mTc pertechnic acid; vi) c collecting the dissolved 99mTc reaction product as a crude solution; and vii) purifying the crude solution containing 99mTc using column chromatography to provide the 99mTc isotope as a radiochemical compound.
In an embodiment, the 99mTc containing reaction product is Tc2O7. In another embodiment, the salt of the 99mTc product is sodium pertechnetate (Na99mTcO4) in saline solution.
In another embodiment, an apparatus for separation of radioisotopes is provided which includes: i) a dissolution cell for placing a molybdenum target for heating and dissolution; ii) a thermal separation unit including a reaction vessel to separate radioisotopes; iii) a vacuum line connected to the thermal separation unit to reduce the pressure for sublimation; and iv) a condenser unit connected to the thermal separation unit associated with a collection vial to collect the condensed product.
In another embodiment, the condenser unit is a U-shaped thermal separation tube.
In another embodiment, the apparatus for separation of radioisotopes includes a purification unit, which includes a plurality of chromatographic units and reagent reservoirs.
In another embodiment, the system is designed to be used for routine production of 99mTc by a cyclotron and to be installed in a medical unit handling radiopharmaceutical products.
These and other features of the present invention will become readily apparent upon further review of the following specification and drawings.
Unless otherwise indicated, similar reference characters denote corresponding features consistently throughout the attached drawings.
The disclosure relates to apparatuses and methods for the thermal separation of Technetium-99m (99mTc) from molybdenum targets including the combined vacuum evaporation and thermal distillation processes to isolate 99mTc from a multicomponent system that is generated at the molybdenum target.
As used herein, the term “thermal separation” refers to a mass transfer process in which species are separated because of differences in volatility. The term “thermos-chromatography” refers to a process in which the separation occurs in the gas phase, wherein a gas is passed through a negative thermal gradient along a column. Separation of species in the chemical components in gaseous state gas occurs because of their different volatilization temperatures: the less volatile species will condense on the column walls at the higher temperatures and the highly volatile compounds will condense at the lower temperatures. Thus, this difference in volatilization temperature can be used to separate the radioactive isotope from a multicomponent mixture.
The production of radiochemical products as precursors for radiopharmaceutical formulation typically requires multiple steps. The formulation of a radiochemical product as a radiopharmaceutical compound must take into consideration compliance with Pharmacopoeia monographs for the desired product. The manufacturing process of radiopharmaceutical products must be fast compared with the radioactive half-life, easy to operate in a radioactive environment, and reliable for providing a good manufacturing practice (GMP)-compliant compound, for example.
99mTc can typically be directly produced by irradiating a solid molybdenum target material deposited onto a substrate with a proton beam at different energies. Referring to FIG. 1, an embodiment of an exemplary process 1000 for production of medical radioisotopes includes the irradiation of exemplary enriched material to produce the desired isotope (step 10), pre-oxidation and dissolution of the irradiated target material (step 20) into a designated dissolution unit and then transferring the obtained mixture from the dissolution unit to the separation or synthesis unit (step 30). Once the mixture is received in the separation or synthesis unit, the material is evaporated under vacuum (step 40) to remove excess water and then subjected to oxidation (step 50). The volatile compounds generated during the oxidation process are collected (step 60) and thermally separated in an oxidizing atmosphere under gas flow and purified (step 70). The desired 99mTc is recovered by using various suitable separation techniques, such as liquid chromatography (step 80).
As illustrated above, the method for separating 99mTc isotope from a molybdenum targets includes providing an initial multicomponent mixture containing 99mTc. The multicomponent mixture of elements is then dissolved in an oxidizing agent to oxidize the mixture of elements. This step is followed by heating the mixture of elements at a temperature sufficiently high enough to sublimate the mixture and generate a vaporized compound containing 99mTc. Typically, the next step involves condensing the vaporized compound containing 99mTc to form a reaction product. The 99mTc is recovered by adding a base to the condensed reaction product to dissolve the 99mTc containing reaction product to form a salt of the 99mTc product and then collecting the crude solution of the dissolved 99mTc product. Finally, the salt of the 99mTc product is separated and isolated using column chromatography as a radiochemical compound.
In an exemplary embodiment, the thermal separation process involves isolating the 99mTc produced by a cyclotron irradiation from a multicomponent system including Cu (copper), Mo (Molybdenum), Tc (Technetium) and Nb (Niobium) elements. The 99mTc is directly produced via a 100Mo (p, 2n) reaction by irradiating the enriched 100Mo target material with a proton beam typically at energies between about 10 Megaelectron-volts (MeV) to about 24 MeV with a highest cross section value for production of 99mTc in the range of from about 10 MeV to about 15 MeV, for example.
In another embodiment shown in
For a cyclotron production of 99mTc, the target molybdenum material is represented by a metallic enriched 100Mo material deposited on a passivated high-purity oxygen-free copper (Cu) support. During irradiation, metallic Technetium (Tc) is generated as a product isotope of 100Mo following the 100Mo (p, 2n) 99mTc nuclear reaction. The separation process of Technetium (Tc) from the other components generated during irradiation occurs when the target support plate 103, desirably as a passivated copper support, including the irradiated molybdenum target 101 is exposed to an oxidizing environment and heated at temperature high enough to generate volatile oxides.
Referring to
In an exemplary embodiment of a target transfer unit and a dissolution unit 4000 as shown in
Referring to the Molybdenum (Mo) and Technetium (Tc) separation, the process involves the initial oxidation of the irradiated molybdenum material by dissolving in H2O2, evaporating and heating the residue material at a suitable temperature to induce the formation of volatile compounds. The complete oxidation of the elements in the mixture desirably occurs at a temperature range of from about 600° C. to about 1200° C. Typically, the heating is conducted under a reduced pressure created by a vacuum line, for example.
In the presence of oxygen, the existing Tc in the mixture is oxidized when exposed to temperatures greater than 500° C. to its oxide form, Tc2O7 (boiling point 310.6° C.; melting point 110.9° C.) as the anhydride of the pertechnic acid produced by following the reaction:
4Tc(s)+702(g)→2Tc2O7(g) (1).
The existing Mo in the mixture is oxidized when exposed to temperatures higher than 500° C. to molybdenum trioxide MoO3 by following the reaction:
Mo(s)+3/2O2(g)→MoO3(s) (2).
The Tc2O7 compound has a saturated vapor pressure of 101 kPa (kilo Pascals) at a temperature of 310° C., while the molybdenum trioxide has a similar vapor pressure at a temperature of 700° C. As the volatilization process continues, the formed volatile oxides are carried out by the gas stream through the U-shaped thermal separation tube to the relatively coolest regions as typically dictated by a thermal gradient.
An embodiment of an apparatus for separation of radioisotopes typically includes a dissolution cell for placing a molybdenum target for heating and dissolution and a thermal separation unit including a reaction vessel to separate radioisotopes. Additionally, a vacuum line can be connected to the thermal separation unit to reduce the temperature for sublimation. Also, typically a condenser unit is connected to the thermal separation unit having a collection vial to collect the condensed product for further separation.
Referring now to
The reaction chamber 50 can be manufactured from quartz, ceramics or any other chemically inert material suitable for operation at relatively high working temperatures (such as up to 1200° C.). The reaction chamber 50 is embedded into a ceramic insulation bed including heating elements 46. In an exemplary system, the reaction vessel or reaction chamber 50 is equipped with the admission tube 44 for an isotopic mixture, as well as an oxygen oxidizing gas which can be, but is not limited to, oxygen, air, moistened air, or combinations thereof. In the exemplary system, the reaction chamber 50 can have a diameter of about 50 millimeters (mm), for example. The working temperature is typically controlled by external temperature controllers connected to internal thermocouples, for example. A funnel shape condenser 53 captures the volatile vapors of Tc2O7 formed during the oxidation process at temperatures higher than 560° C., for example. The exemplary condenser 53 can have a straight region of a larger diameter and followed by an angled region 54 at the exit of the heating zone. For facilitating the vapor collection, the outer diameter of the condenser 53 can be reduced to about 25 mm, for example. The straight region of the condenser 53 will be heated up to a temperature in a range of from about 400° C. to about 600° C. to keep the Tc2O7 in a gaseous state while the angled region 54 is cooler as well as to maintain a temperature gradient along the thermal separation system. At the same time, the volatile MoO3 oxide remains at a temperature in the region in a range of from about 600° C. to about 700° C. The process optimization trials indicate that the Tc2O7 vapors are condensed at temperature below 200° C. at the outer end of the heating zone. The end part of the thermal separation system is desirably designed as a straight tube with outer diameter of about 8 mm. The condensed Tc2O7 vapors dissolved in diluted NaOH solution is transferred to the collection vial. As an anhydride of the pertechnic acid HTcO4, Tc2O7 shows a relatively high affinity to water. Thus, the Tc2O7 will be dissolved in a liquid and transformed to NaTcO4, as follows:
Tc2O7(g)+2NaOH(aq)→2NaTcO4(aq)+H2O(aq) (3).
A collection vial 52 can contain a diluted NaOH solution, or saline, water or any other suitable capturing solution used in pharmaceutical formulation, for example. In other embodiments, the base can be a dilute potassium hydroxide solution, for example. The obtained NaTcO4 is vacuum transferred from the collection vial 52 to the pharma unit 62 for additional purification by liquid chromatography.
In another exemplary embodiment of the apparatus 5000 shown in
Referring now to
In an exemplary embodiment, the thermal separation unit and the pharma unit 62 as a purification unit are embedded in a lead shielded enclosure, for example.
In an exemplary embodiment, the radioactivity is monitored during the separation process through the radiation detectors 56 placed in the thermal separation unit 42 and the pharma unit 62, for example.
In an exemplary embodiment, the pharma unit 62 includes solenoid valves 94, 96, 98, 100, 102, 104, 106, 108, 110 and 112 and the reagent reservoirs 64 containing United States Pharmacopeia (USP) grade chemicals used for a pharmaceutical formulation. The radiopharmaceutical precursor is collected in a product vial 70 as a radioactive solution, which is typically detected by the radioactive detector 56 placed in the vicinity of the product vial 70.
In an exemplary embodiment, the sodium pertechnetate solution can be transferred to the chromatographic column for an additional purification process. This transfer can be achieved by opening the valves 98, 110, 88, 82 and 112 to the product vial 70. At the end of the transferring step, the lines are dried by purging inert gas into the system by turning on admission valves 108, 106, 104, 100 and 112 at a pressure in a range of from about 5 psi (pounds per square inch) to about 15 psi, for example.
Typically, in an exemplary embodiment, the separating of the 99mTc is carried out in a thermal gradient under differential pressure conditions, for example.
At the end of the separation process, the compound is formulated as a radiopharmaceutical precursor by adding the United States Pharmacopeia (USP) compliant reagents. The product is recovered into a closed vial as a radiopharmaceutical precursor in the product vial 70.
In another embodiment, the retained radioisotope can be elutriated from the chromatographic column by elution with the reagents from the reservoirs 64 and opening the valve 96 and three way valve 112 to a waste vial 72. Although a saline solution is the desired eluent, other solutions such as NaHCO3, H2O, diluted NaOH, HCl, ethanol or various combinations thereof can be used. In some embodiments, the purification step can include multiple washing steps, for example.
An apparatus for separation of radioisotopes typically includes a dissolution cell, such as the dissolution unit or module 22 for placing a molybdenum target for heating and dissolution; a thermal separation unit, such as the thermal separation unit 42, including a reaction vessel, such as the reaction chamber 50, to separate radioisotopes; a vacuum line connected to the thermal separation unit to reduce the temperature for sublimation; and a condenser unit, such as the condenser 53, connected to the thermal separation unit having a collection vial, such as the collection vial 52, to collect the condensed product.
In an alternate embodiment,
In an exemplary embodiment, the admission tube or admission port 44 is coupled directly to a dissolution cell, for example. Typically, the admission tube is coupled to an oxygen line.
In an exemplary embodiment, the condenser unit, such as the condenser 53, has a variable diameter and is angled to a collection flask, such as the collection vial 52, located outside the thermal separation unit 42a, for example.
The reaction chamber 50 and the thermal separation column 54a can be made from quartz, ceramic or other chemically inert material suitable for operation at relatively high working temperatures (such as 1100° C.). Once the separation is completed, the reaction chamber 50 is cooled rapidly with forced air through a ventilation tube 60 located in the bottom part of the separation unit. In an exemplary embodiment, the collection vial, such as the collection vial 52, is coupled to a vacuum line, for example.
Referring to the
In another exemplary embodiment of the process, as shown in
In another embodiment, molybdenum is recovered at the end of the process. The reaction chamber 50 can be washed with ammonium hydroxide or sodium hydroxide solution to convert the MoO3 to ammonium molybdate or alternatively sodium molybdate.
Running the separation procedure at high temperature permits the collection of molybdenum from the reaction chamber 50 for a recycling and reprocessing procedure, for example.
In another exemplary embodiment, the copper can be removed from the system by running a cleanup procedure. As copper does not typically present oxides with volatilization temperatures of 850° C. or below, the traces of copper oxides remain in the reaction chamber 50 and can be removed from the system by running a cleanup procedure, such as with hydrochloric acid. Finally, the system is rinsed with ultra-pure water (Optima LC/MS grade) and dried by purging inert gas through the lines, for example.
In an embodiment, the thermal separation unit 42 and pharma unit 62 are accommodated in a shielded enclosure, such as lead lined aluminum enclosure. For running the separation procedure of 99mTc from a multicomponent system including Mo/Tc/Cu, the system described can be automated for remotely controlling the process such as by a controller 85 in communication with the separation apparatus, such as the apparatus 6000 or the apparatus 8000, such as through a ladder logic controller as a programmable logic controller (PLC) for the controller 85 and as can be operated externally and remotely of the system, for example. The controller 85 can include or be associated with a processor for execution of instructions for system control, a memory for storing programs and instructions used by the processor for remote or automatic control and operation of the system of the separation apparatus, and an input device or interface to send or receive information and instructions for system control and operation, for example.
Referring to
In an embodiment of the apparatus 8000, the injection system is used to collect the condensed material by collection from the bottom part of the condenser unit, such as the condenser 53, for example.
Referring to
Referring to the multi component Mo/Tc separation, the oxidation process occurs as a competitive reaction between Cu oxides formation and Mo/Tc oxidation. By direct exposure of a molybdenum (Mo) target support plate in the oxygen flow, the oxidation mechanism typically involves three sequential steps: (1) adsorption of O2 molecules onto a metallic surface; (2) oxidation of metals; and (3) oxide separation based on the volatilization temperatures. The oxidation process of Cu typically involves two phases: the partial oxidation with formation of Cu2O and total oxidation with formation of CuO. The formation of these two oxides inhibits the formation of Tc2O7 and its transportation to the cooler regions of the quartz tube forming the separation column 54a; and, hence, its condensation in the region of temperatures below 300° C. About 50% of radioactivity has been found on the target insertion point either as a Tc2O7:MoO3 mixture or trapped on the copper layers, most probably as Cu(TcO4)2, embedded in the Cu2O lattice. This can be explained by the formation of Cu2O in the first oxidation phase, which is competing with the oxidation of Mo and Tc. A concurrent reaction with an inhibiting effect on the separation process can be the reaction between CuO and MoO3 with formation of CuMoO4 (yellow-green) at a temperature in a range of from about 500° C. to about 700° C., for example.
Significant improvements to reduce the effect of copper on the separation of molybdenum (Mo) and Technetium (Tc) have been made by including the pre-oxidation step in the process. Once the irradiated target is dissolved with NaOH, H2O2 (hydrogen peroxide) or other oxidative agent including nitric acid (HNO3) or sulfuric acid (H2SO4), the existing elements are partially oxidized. Hence, molybdenum (Mo) is converted in a mixture of peroxomolybdates and Tc is converted to pertechnetate [TcO4]−. The partial oxidation of copper in an acidic medium of molybdic (MoO42−) and pertechnic (TcO4−) acidic mixture leads to the formation of Cu2+ according to the reaction being identified most likely as Cu(OH)2, as follows:
Cu(s)+H2O2(aq)+2H+(aq)=Cu2+(aq)+2H2O(l), (4),
with an equilibrium constant of K=1048.6 at 25° C.
The oxidation process of copper by H2O2 is typically rather slow. For example, 17.5 micrograms/milliliter (μg/mL) of copper has been found in solution after exposing 5 grams of a Cu disk to 8.5 mL of 30% H2O2 for 30 minutes. This chemical behavior of constitutive elements has been used to improve the exemplary separation system. Thus, the Mo and Tc can be easily dissolved by peroxide or NaOH solution but dissolution of copper occurs at a lower rate. The peroxide solution containing Mo and Tc are evaporated leaving the Mo and Tc for further oxidation by flowing oxygen at relatively high temperatures. Thus, the two step oxidation process essentially eliminates the Cu from the final product. As discussed above, washing with sodium hydroxide (NaOH) at the end of the process resulted in 99mTc as Na 99mTcO4, with recovery of radioactivity greater than 70%, for example.
In an exemplary embodiment, the apparatus, such as described herein, for separating the Technetium (Tc) is controlled externally by an operator to separate the radioisotopes, for example.
In an exemplary embodiment, the liquid circulation into the separation process is made though electric actuated valves in the apparatus, such as the valves in the apparatus 6000 and in the apparatus 8000, for example.
In an exemplary embodiment, the apparatus for separation of radioisotopes typically includes an operational procedure that allows Molybdenum recovery from the separation process.
Another significant improvement to reduce the contribution of Copper to the Mo/Tc separation process has been made by adding a passive layer of chemically inert material (such as noble metals) on the surface of copper target support plate, such as the target support plate 103. For example, a gold layer having a thickness in a range of from about 3 μm (microns) to about 5 μm (microns) has been electroplated on the copper support as a passivation layer. The molybdenum material, such as a Mo-100 material, is attached to the protected passivated copper target support plate 103. For example, a molybdenum (Mo) target 101 on a copper target support plate 103 having a passivation layer has been dissolved with about 3 mL of a 30% H2O2 solution and the formation of copper ions in the solution has been checked. No traces of copper have been identified in the solution. In one exemplary embodiment of this thermal separation process, the Mo/Tc/Cu separation process includes the thermal separation unit 42a accommodating a U-shape thermal separation tube 54a designed for separation in a temperature gradient.
The following examples are provided to illustrate the operational use of the described embodiments of exemplary systems and processes for a Mo/Tc thermal separation, but should not be construed in a limiting sense.
Mo/Tc thermal separation performed on a simulated multi component system. A mixture obtained from dissolution of Mo target from a copper plate with about 5 mL of 30% H2O2 has been spiked with commercially available 99mTc. The volume of the obtained solution has been reduced to 3 mL by gentle evaporation and introduced in the reaction chamber 50. The temperature was set at 120° C. and the vacuum pump was turned on. After about 15 min the evaporation is complete as it can be observed by a temperature increase at the end of the process. After the evaporation step ended, the temperature was raised to 700° C. and oxidizing gas was introduced at a flow rate of about 10 mL/min to 20 mL/min through the radioactive mixture containing commercial available 99mTc (Isologic) as sodium pertechnetate in saline solution. The radioactivity has been monitored at the collection port 61 of the apparatus 8000 in
Mo/Tc thermal separation from a multicomponent isotopic mixture obtained via a 100Mo(p,2n)99mTc nuclear reaction generated on a 100Mo target.
192.5 mg Mo-100 (Isoflex, 99.03%) target material was deposited as a pellet with the diameter of 0.8 cm onto a 2.5 cm diameter copper disc (oxygen free) to produce 99mTc by the nuclear reaction 100Mo(p,2n)99mTc. The disc was irradiated for 30 minutes with a 15 MeV proton beam produced by a particle accelerator. The current intensity of about 65 μA (microamperes) was used. After irradiation, the activity detected on the disc was about 34.5 GBq (Giga Becquerel) counted at 90 minutes end of bombardment (EOB) and drastically decreased in the first two hours from EOB indicating the presence of high amounts of short half-life isotopes such as: 94mTc (T1/2=52.01 min), 96mTc (T1/2=51.51 min), 97Nb (T1/2=72 min). At the end of the process, the irradiated target was dissolved with 5 mL 30% H2O2 and the volume reduced to about 2 mL. The isotopic mixture containing Mo, Tc, Nb and Cu was transferred to the reaction chamber 50. The vacuum evaporation was completed in about 10 minutes at the temperature of 120° C. After completion of the evaporation phase, the oxidation started at the temperature of 700° C. in the presence of oxygen (O2) gas at a flow rate of 20 mL/min. The oxidation process was run for about 30 min. At the end of the process, Tc was collected from the thermal separation column 54a by quantitative rinsing with about 5 mL of 0.1M NaOH. The radiochemical analysis performed on the purified product by radio Thin Layer Chromatography (radio TLC scanning system Raytest mini Gita, stationary phase: Silica Gel-PET plates Polygram SILG, mobile phase acetone) indicating the presence of 99mTc as pertechnetate Retention Factor (Rf)=0.9±0.1.
Surprisingly, embodiments of the thermal separation process can provide several advantages. Since embodiments of the described thermal separation apparatus can be automated, it can be an online system which can be relatively easy to operate and can be remotely controlled, for example. Also, the thermal separation apparatus is relatively compact and can be installed inside a relatively small hot cell near a nuclear medicine center, which can be advantageous for continued operation. Moreover, embodiments of the processes can be modified for other thermal separation processes, such as Iodine-124, and should not be construed in a limiting sense. Additionally, the embodiments of the processes can use a reduced number of chemicals and reagents used in the separation process, and advantageously can typically avoid the use of limited and expensive purification resins, for example.
Also, the final separated product Na99mTcO4 from the separation process was highly pure containing only the Tc isotopes with no apparent traces of zinc, copper or contaminating metals, for example.
A sample aliquot of the separated product of the described process has been used to produce a point source with the activity of about 370 kBq (kilo Becquerel) which was assessed to determine the radionuclidic composition of the purified product by gamma spectrometry performed on a Gamma Spectrometer (Baltic Scientific Instruments, hyper pure germanium (HPGe) coaxial detector, p type, equipped with Interwinner Software).
As a result of the assessment and determination, only Technetium isotopes have been identified in the analyzed sample, as shown in Table 1 below.
93Tc
94Tc
95Tc
96Tc
97Tc
99Mo
The obtained radioisotopic profile of the assessed sample aliquot of the separated product was analyzed against the gamma spectrum acquired from an identical aliquot (point source 370 kBq) sampled from the crude solution. The presence of Niobium isotopes Nb-97 (T1/2=72 min) were identified in the raw material (ratio Nb-97/Tc-99m 2.07%) in the spectrum acquired at 368 min EOB. However, the presence of other Nb isotopes (e.g., Nb-95) could not be certified in the given sample. In a highly oxidative environment niobium (Nb) is oxidized as Nb2O5 and remains in solid state in the reaction chamber. Niobium pentoxide (Nb2O5) was not retrieved in the rinsing solution of the reaction chamber 50 as the reaction between Nb2O5 and NaOH with the formation of sodium niobate (NaNbO3) occurs at temperatures higher than 200° C.
It is to be understood that the present invention is not limited to the embodiments described above, but encompasses any and all embodiments within the scope of the following claims.
The present invention claims priority to U.S. Provisional Application Ser. No. 62/035,589, filed Aug. 11, 2014, which is incorporated by reference herein in its entirety.
| Filing Document | Filing Date | Country | Kind |
|---|---|---|---|
| PCT/CA2015/050748 | 8/7/2015 | WO | 00 |
| Number | Date | Country | |
|---|---|---|---|
| 62035589 | Aug 2014 | US |
