阅读说明：本技术 由Ra-226生产Ac-225的方法 (Method for producing Ac-225 from Ra-226 ) 是由 约瑟夫·科莫 让·米歇尔·吉茨 格德·约尔根·贝耶 于 2020-11-26 设计创作，主要内容包括：一种由Ra-226生产Ac-225的方法,其中所述Ra-226以液体溶液的形式存在于容器中,所述Ra-226经受光核过程,其中Ra-226(γ,n)被辐照以产生Ra-225,然后所述Ra-225衰变为Ac-225,所形成的Ac-225通过其在存在于所述容器中的阴极上的电化学沉积而被收集,在所述沉淀发生后,从所述容器中取出所述阴极,并放入热电池环境,在所述热电池环境中从所述阴极上提取所述Ac-225。(A method of producing Ac-225 from Ra-226, wherein the Ra-226 is present in a container in the form of a liquid solution, the Ra-226 is subjected to a photonuclear process in which Ra-226(γ, n) is irradiated to produce Ra-225, the Ra-225 then decays to Ac-225, the Ac-225 formed is collected by its electrochemical deposition on a cathode present in the container, after the deposition has taken place, the cathode is removed from the container and placed in a thermal battery environment, and the Ac-225 is extracted from the cathode in the thermal battery environment.)

1. A method for producing Ac-225 from Ra-226, wherein the Ra-226 is present in a container (2) in the form of a liquid solution, the Ra-226 is subjected to a photonuclear process wherein the Ra-226(γ, n) is irradiated to produce Ra-225, and then the Ra-225 decays to Ac-225, characterized in that,

the formed Ac-225 is collected by electrochemical deposition thereof on a cathode (5) present in the container, after said deposition has taken place, the cathode is removed from the container and placed in a thermal battery environment (4) in which the Ac-225 is extracted from the cathode.

2. The method of claim 1, wherein the Ra-226 is irradiated with photons of at least 6.4MeV in energy, the photons being generated by bremsstrahlung from an electron beam of energy higher than 6.4 MeV.

3. The method according to claim 1 or 2, characterized in that the cathode on which Ac-225 is deposited is made of a chemically inert metal, preferably Au, Ta, W, Nb, Rh, Pt or Ir or alloys thereof.

4. The method of any one of claims 1 to 3, wherein the Ac-225 extracted from the cathode is purified to remove traces of co-precipitated Ra-226 and Ra-225.

5. The method according to any one of claims 1 to 4, wherein the liquid solution in which Ra-226 is present is HNO having a pH of less than 6₃Solution, preferably HNO having a pH of 1 to 4₃And (3) solution.

6. A method according to any one of claims 1 to 5, characterized in that the containers comprise a first container (2) and a third container, which first container (2) and third container are interconnected in such a way that the Ra-226 solution can flow from the first container to the third container, in which third container the cathode is placed.

7. The method of any one of claims 1 to 6, wherein the electrochemical deposition of the formed Ac-225 is performed during irradiation with Ra-226.

8. The method of any one of claims 1 to 7, wherein a plurality of separate first vessels are used for electrochemical deposition of the formed Ac-225.

9. A method according to any one of claims 1 to 8, characterized in that the electrochemical deposition is carried out batchwise and that the irradiation is interrupted when the cathode enters the environment of the thermal battery.

10. The method according to any one of claims 1 to 9, characterized in that the liquid solution is purged with a flow of inert gas, in particular He.

Technical Field

The present invention relates to a process for the production of Ac-225 from Ra-226, wherein the Ra-226 is present in a container (recipient) in the form of a liquid solution, the Ra-226 is subjected to a photo-nuclear process in which the Ra-226(γ, n) is irradiated to produce Ra-225, and the Ra-225 is then attenuated to Ac-225.

Background

Such a process is known from WO 01/41154. According to this known method, a solution containing Ra-226 is placed in a container, and then an electron beam is directed at the conversion material to generate photons. Photons are then directed at Ra-226 to undergo a photoinduced transmutation reaction to form Ra-225, which decays to Ac-225. The Ac-225 thus obtained can then be collected by wet chemistry using an ion exchange column.

One disadvantage of this known method is that it requires a radiochemical procedure to recover the target Ra-226. This recovery is time consuming and involves a very dangerous process, since Ra-226 is a highly radioactive substance.

Disclosure of Invention

It is an object of the present invention to avoid the recovery of Ra-226 after chemical separation of Ac-225.

To this end, the method of the invention is characterized in that the Ac-225 formed is collected by its electrochemical deposition on a cathode present in the container, and after the deposition has taken place, the cathode is removed from the container and placed in a hot cell environment (hot cell environment) in which the Ac-225 is extracted from the cathode. After the deposition has occurred, the irradiated Ra-226 target need not be transferred, but rather only the cathode containing the electrodeposited Ac-225 is removed from the container and placed in a suitable thermal cell environment where the Ac-225 is extracted from the cathode. Since Ra-226 remains in the container and since only the cathode containing the deposited Ac-225 is transferred, a significantly smaller thermal cell environment is required to obtain Ac-225 from the cathode. Ra-226 was left in the vessel ready for continued irradiation procedures without the need to apply any recovery protocol.

It should be noted that electrochemical deposition using radionuclides on the cathode is known. Lange et al, article "Die Darstellung von Strontium-90-freieem Yttrium-90durch Electrolysis", J.Inorg.Nucl.chem.4(1956), p.146-154, describe such an electrochemical deposition to obtain Y-90 starting from Sr-90. However, the start-up conditions of these two processes are very different. The half-life of Sr-90 is 28.79 years, while the half-life of Ra-226 is 1600 years. This means that if Sr and Ra of the same activity are present in the solution, the physical quantity (atomic number) of radium is 55.57 times higher than that of strontium 1600/28.79, i.e. if the solution is considered, the radium concentration is 55.57 times higher than that of strontium. For this reason, the skilled person handling Ac-225 obtained from Ra-226 would not consider this prior art to be relevant. The cited prior art relating to Sr-90/Y-90 generators solves the problem of selectively separating Y-90 from the Sr-90/Y-90 solution using a minimum amount of chemicals in the overall process, so that the Sr-90/Y-90 generator can be used in a hospital radiopharmacy (hospital radio-pharmacy). The teachings of this document do not relate to the development of an isotope production process by irradiation, nor do they consider the recovery of the Sr-90 source.

A first preferred embodiment of the method of the invention is characterized in that said Ra-226 is irradiated with photons of energy of at least 6.4MeV, said photons being generated by Bremsstrahlung (Bremsstrahlung) of an electron beam of energy higher than 6.4 MeV. In this way a dense photon beam is generated, so that a sufficient amount of Ac-225 can be formed.

A second preferred embodiment of the process of the invention is characterized in that said Ac-225 extracted from said cathode is subjected to chemical purification to remove traces (routes) of coprecipitated Ra-226 and Ra-225.

Drawings

The invention will now be described in more detail hereinafter with reference to the accompanying drawings. In the drawings:

FIG. 1 shows an overview of the decay chain of U-233 and the different methods of producing Ac-225; and

fig. 2 shows a schematic example of an apparatus that can be used to implement the method of the present invention.

Detailed Description

The alpha-emitting radionuclide Ac-225 and its daughter Bi-213 have been successfully used in systemic Targeted Alpha Therapy (TAT), as published by Scheinberg D.A. and McDeit R. "Actinium in targeted alpha-particulate therapeutic application", Currrradiopharm.2017; 211(4), page 306 and 320 (https:// www.ncbi.nlm.nih.gov/PMC/articules/PMC 5565267 /). Significant success has recently been achieved in the treatment of metastatic prostate cancer using Ac-225. Thus, this success has led to a high demand for Ac-225. However, the current worldwide production of Ac-225 is far from meeting the demand for this important radionuclide.

FIG. 1 shows an overview of the U-233 decay chain and the different methods of producing Ac-225. There are three main strategies for the production of Ac-225. The first is the indirect production of Ac-225 by alpha-decay of Th-229. The second is the indirect production of Ac-225 by beta-decay of Ra-225, and the third is the direct production of Ac-225.

Ac-225 used to date has been mostly isolated from Th-229, which was obtained during the cold warfare period by the breeding process of Th-232(n, γ) Pa-233 → U-233. Currently, the available inventory for Th-229 in Oakridge (USA) is about 5GBq, and the available inventory in Karlsruhe is about 1.7 GBq. In Obninsk (Russia), a small amount of Ac-225 was isolated from U-233 (Boll R.A., Malkemus D., Mirzadeh S., Production of expression-225 for alpha particulate media radioimmunotherapy, applied. radial. Isot.2005; 62: 667-.

Reprocessing of several tons of U-233 to separate Th-229 that grows simultaneously is technically complicated due to limitations in handling fissionable materials. Only very small amounts of U-233 material can be processed in one process batch and the amount of extractable Th-229 is very small. Thus, the overall cost of such a process would be unacceptably high and the time frame would be unacceptably long.

Techniques for the direct production of Ac-225 by high-energy proton induction reactions have been developed in Troitzk (near moshow) (b.l.zhuikov, s.n.kalmykov, s.v.ermolaev, r.a.aliev, v.m.kokhanyuk, v.l.matushko, i.g.tanauev, b.f.myasoedov,2011, published in Radiokhimiya, 2011, vol 53, No. 1, p.66-72). Then transferred to the United states where the Brookhaven-Los Alamos-Oakridge national laboratory collaboration provided users with Ac-225 produced according to this reaction on a regular basis in amounts up to 1 Ci. The disadvantage of this approach is that the nuclear reaction also produces an amount of Ac-227 that is unacceptable for direct use of Ac-225 for therapeutic purposes.

One promising approach to produce Ac-225 is an indirect production route via photonuclear processes: ra-226 (gamma, n) → Ra-225 → Ac-225. This method is described in WO 01/41154 and has been experimentally demonstrated to produce Ci-active Ac-225 under realistic practical conditions. According to known methods, approximately 1g of an Ra-226 target is placed in a container, and then an electron beam is directed at the conversion material to generate photons. The photons are directed at the Ra-226 target, causing a light induced transmutation reaction and the formation of Ra-225 on the target. This initially produced Ra-225 decays to the desired product Ac-225. The Ac-225 thus obtained can then be separated using simple wet-chemical methods, for example using ion exchange columns. Allen b.j. et al compare the proton-induced reaction of the mentioned photonuclear process Ra-226(γ, n) → Ra-225 with Ra-226(p,2n) → Ac-225 on a compact Cyclotron using Ra-226 as the target, concluding that the photonuclear reaction is very advantageous, since it is possible to use a large amount of Ra-226 and to perform irradiation in solution (Melville g., Allen b.j.et.al, "Cyclotron and line Production of Ac-225" Applied radiation.

The technical production scheme for the manufacture of Ac-225 from Ra-226 is similar, i.e. the preparation of small Ra-226 targets (-1 g) meeting all safety requirements, the irradiation process and the transfer of the irradiated targets into the corresponding thermal battery environment for processing, according to the photonuclear process or the direct proton based Ra-226(p,2n) -process using a cyclotron based Ra-226(p,2 n). The only difference is that in the case of the photonuclear reaction, it is necessary to wait approximately 8 days for the desired Ac-225 to grow from the decay of the initially formed Ra-225.

Radiochemical processes including dissolution and chromatographic separation and purification of the final Ac-225 product are easy to implement. However, the remaining Ra-226 solution thereafter needs to be recovered and converted to a new Ra-226 target for the next irradiation and production cycle. This recovery process is very dangerous as part of each production process, since it involves the handling of highly radioactive material Ra-226. The recovery process is also time consuming.

In accordance with the present invention, such a Ra-226 recovery process can be avoided by selectively extracting the Ac-225 obtained from the irradiated Ra-226 source, thereby leaving the Ra-226 source in the vessel in which the photonuclear irradiation process is occurring. The present invention proposes a method wherein only the Ac-225 obtained after irradiation is transferred without the need to transfer the Ra-226 source or the fully irradiated Ra-226 solution to the place where the radiochemical separation process should be performed. Irradiation of Ra-226 can continue immediately after Ac-225 is isolated without any further recovery operations. The separation process itself is based on the selective electrochemical deposition of Ac-225 on a cathode electrode, in particular made of Au, Ta, W, Nb, Rh, Pt or Ir or alloys thereof.

Fig. 2 schematically shows an example of an apparatus for the electrochemical separation process. The device comprises a first container (2), wherein Ra-226 is present as a liquid solution in the first container (2). The first vessel constitutes a reaction vessel and is made of a radiation-resistant material such as metal, quartz, glass or ceramic. The first container is irradiated by using a photonuclear source (1), to which photonuclear source (1) an electron beam (3) is directed. A photonuclear source (1) as an electron-photon converter comprises a conversion material, such as tungsten or tantalum, which is aligned by an electron beam (3) to generate photons that will irradiate the Ra-226 solution present in the first vessel. The electron beam is generated by, for example, an electron accelerator (8). The first vessel is preferably irradiated with high energy photons of at least 6.4MeV, the high energy photons being generated by bremsstrahlung from a strong electron beam of energy higher than 6.4 MeV. For example, an electron beam with an energy of 18MeV will produce photons of this energy distribution via bremsstrahlung radiation, so approximately 25% of the photons are suitable for Ac-225 production. Increasing the energy of the electron beam to 40MeV increases the proportion of photons suitable for Ac-225 production to 56%. Increasing the electron energy above 40MeV only slightly increases the Ac-225 production, but causes other competing nuclear reactions, such as 11.3MeV (γ,2n), 17.8MeV (γ,3n) and 23.0MeV (γ,4n) for the threshold photon energy.

The cathode (5) is detachably mounted in the first container (2). The device further comprises a second container (4) separate from the first container. The cathode (5) can be removed from the first container and placed in a second container as indicated by arrow (9). The cathode transfer is arranged in a tight and shielding manner, avoiding leakage of radioactive material. The cathode is preferably a Winkler electrode, rod, sheet or wire. The container itself may form the anode. The irradiation passed through the anode and current between the anode and cathode caused Ac-225 to flow to the cathode.

Instead of using only one first container, the first container (2) may also be connected to a third container (not shown in the figures) so that the Ra-226 solution can be circulated (circular) from the first container to the third container. The third container is then preferably made of the same material as the first container. In the latter embodiment, the cathode will be placed in a third vessel during the irradiation process.

The apparatus preferably further comprises a cleaning station (7) separate from the first and second containers. The cleaning station is used to remove impurities in the Ac-225, mainly co-precipitated trace amounts of target material itself and Ra-225 produced in the photonuclear reaction. The second container (4) and the cleaning station (7) are preferably housed in a closed (confined) environment (6) so as to greatly limit the risk of nuclear radiation to the external environment.

In this apparatus, the Ra-226 solution was photonuclear irradiated to form Ra-225. The Ac-225 is then transformed by radioactive decay of Ra-225 into Ac-225 and collected by electrochemical deposition on the cathode (5) of the first vessel. After electrodeposition has taken place, the cathode is removed from the first container and placed in a second container (4) remote from the first container. The collected Ac-225 is separated from the cathode in a thermoelectric cell environment formed by the second vessel. The harvesting process is primarily performed without interfering with the primary Ra-226 activity used during irradiation. The original Ra-226 target solution remains in the first vessel and irradiation can continue without further treatment of the Ra-226.

One great advantage of the present invention is that a large amount of Ra-226 has never been treated in the second vessel, which constitutes the environment for the separation of Ac-225. This means that the radiation safety requirements for transferring and handling cathodes containing Ac-225 are more easily met than for handling large amounts of Ra-226. Furthermore, the radiation safety issues associated with the construction and operation of thermal batteries in which cathodes containing precipitated Ac-225 were processed were also significantly less, since only trace amounts of Ra-226 were present in the thermal batteries.

From the experimental data of the electrochemical separation process it can be concluded that:

the higher the current density at the cathode surface, the faster the Ac-225 is deposited.

The lower the pH, the faster the deposition rate. The pH is preferably below 6, more particularly 1-4.

The lower the current density, the less the pH change of the solution. The optimal current density is 20-300 mA/cm²。

The smaller the ratio between the sample volume and the cathode surface, the higher the deposition yield.

The higher the current density, the more the temperature of the solution increases. The temperature increase has a significant effect on the deposition rate.

The Ra-226 present in the first vessel is preferably in nitric acid (HNO)₃) Irradiating in the solution. The volume of the target solution can vary from 50mL to several liters. The volume depends on the amount of Ra-226 target that should be irradiated. The concentration of Ra-226 in the nitric acid solution can be as high as 0.2M, corresponding to about 50g of Ra-226 per liter. The pH of the nitric acid solution is preferably below 6, more preferably 1-4, preferably with HNO₃And (6) adjusting. In an electrochemical extraction process, the pH may be slightly increased. As long as the pH is below 6, more preferably 1-4, the change in pH has no effect on the electrochemical separation efficiency. However, it is preferred to add 1M HNO in a sufficiently small volume₃From time to time (e.g., after 10-20 production runs) the pH is controlled and corrected. By doing so, the electrochemical deposition rate will remain at its maximum.

Typically, two electrodes are present in the first vessel in which the electrochemical deposition is carried out. The first electrode serves as an anode and the second electrode serves as a cathode (5). If the container is made of a noble metal, such as platinum or iridium or alloys thereof, the container may be used as the anode. In this case, only the cathode is placed inside the first container. The size of the cathode used for electrochemical deposition mainly determines the rate of Ac-225 deposition. To determine the cathode surface, the volume of the solution to be treated needs to be taken into account.

During the electrochemical process, the temperature of the solution being treated increases. To avoid substantial evaporation of the Ra-226 solution during irradiation and electrolysis, it is preferred to cool the solution. This is achieved, for example, by a cooling station (10) which is provided for cooling the first container (2) and the photonuclear source (1). The temperature is preferably stabilized at a prescribed level, preferably 30 ℃, using a thermostat method. Under these conditions, the electrochemical deposition time increases by more than 90%, but due to the half-life of Ac-225, no strict time limitation is required and electrochemical treatment of one to even a few hours is acceptable.

Three different methods can be applied to implement the method of the invention:

a. batch (batch) production processes;

b. a semi-on-line production method;

c. a continuous production method.

In a batch process during Ra-226 irradiation, Ra-226 is partially converted to Ra-225. The theoretical saturation activity of Ra-225 reached about 50% over about two weeks of irradiation. At the same time, the obtained Ra-225 decayed to Ac-225, reaching a maximum after about 8 days. After which electrochemical deposition is carried out, which lasts for several hours. The cathode containing the deposited Ac-225 is then transferred to a second vessel where the Ac-225 is collected from the cathode. The cathode is then returned to the first container. It is also conceivable to use two or even more containers and to irradiate them alternately with the same irradiation source. After the irradiation period in which one of the containers is irradiated is over, the electron beam may be switched to irradiate the other container. In any case, one batch of Ac-225 can be harvested weekly. The irradiation time interval and the decay period can be flexibly changed according to actual needs.

In the semi-online method, the irradiation is interrupted only for a short time of the extraction process. After a longer period of continuous irradiation, steady state conditions are reached, which means that the synthesis and decay of Ra-225 are virtually in equilibrium. The electron beam was turned off and the electrochemical deposition process was immediately turned on to extract the Ac-225 fraction produced by the decay of Ra-225 during irradiation. After the cathode was transferred for Ac-225 treatment, irradiation continued regardless of the activity of Ra-225 still present. Under this operating method, a new batch of Ac-225 can be extracted weekly.

In a continuous process, the extraction process can be carried out even under irradiation conditions. This option can only be proven in practical situations.

The plated Ac-225 can be dissolved from the cathode with about 1M nitric acid solution or, alternatively, the electrode can be electrochemically switched in a weak acid solution to serve as the anode. The transferred cathode will contain some small amount of Ra-226, about 50 μ L of the original target solution. Any known purification method for Ac-225 may be used, preferably chromatographic separation. The purified Ac-225 is then stored in a suitable container (11).

During irradiation, the acidic Ra-226 solution undergoes some radioactive destruction, thereby forming H₂And O₂. Furthermore, the radioactive gas Rn-222 must be considered from the decay of Ra-226. Thus, at least during electrodeposition of Ac-225, the target solution should preferably be purged with a slow inert gas flow (e.g., He). This means that some of the water vapour in the exhaust gas stream must be treated. The total gas volume to be treated is relatively small, estimated to be about 0.5L/h. The treatment of the exhaust gas may be carried out by: the off-gas is passed through a cooling column (cooling column) installed in reflux mode sufficiently effective that the condensed liquid is quantitatively returned to the first vessel. The cooling temperature should be 1-10 ℃. After passing through the cooler, the exhaust gas will pass through a molecular sieve box (mole sieve cartridge) to capture the last traces of moisture. The exhaust gases are then passed through a charcoal cartridge (charcoal) which is cooled to a temperature below 15 c. This charcoal box traps Rn-222 practically quantitatively. For safety reasons, it is preferable to include a cryogenic trap to extract the last potentially trace amount of Rn-222 from the exhaust gas. The off-gas from the separation and purge process, which is performed separately from the target station, will be treated in the same manner. Released H₂And O₂Are below explosive levels and therefore do not require removal of these gases from the exhaust stream.