Device for recovering medical radioisotopes

Abstract

The invention relates to a device (10) for recovering radioisotopes of interest present in the urine of a patient, the device (10) being intended to be connected to a toilet. The device comprises a urine collector (12), a processing unit (14) and a pressure management system (16). The processing unit (14) comprises a filtration and recovery device (20) for each radioisotope of interest configured to filter and recover the radioisotope of interest, a sorting module (22) connected to the urine collector (12) configured to identify the radioisotope of interest in the collected urine, and a processing module (24) connected to the sorting module (22). The invention relates to a method for collecting urine from a radioactive isotope, comprising the following steps: collecting the urine from a radioactive isotope and guiding the collected urine to a filtration and recovery device (20) corresponding to the detected radioactive isotope, at least one first storage chamber (24) fluidly connected to a filtration and recovery system (20) configured to recover the corresponding radioactive isotope.

Description

Technical Field

[0001] The present invention relates to a device capable of recovering radioactive isotopes from biological fluids. Background Art

[0002] As is well known, nuclear medicine is a medical specialty that uses unsealed radioactive sources for diagnostic and therapeutic purposes.

[0003] More specifically, internal vector radiotherapy (IVR) is a therapeutic branch of nuclear medicine. It has developed rapidly in recent years, especially in the context of treating metastatic prostate cancer by targeting PSMA, i.e., prostate-specific membrane antigen (PSMA), expressed by cancer cells using the so-called " 177 Lu-PSMA".

[0004] During IVR treatment, especially during 177 Lu-PSMA treatment, most of the treatment is administered by injection and excreted through urine. In the prior art, this radioactivity is then stored and subsequently discharged into nature when a regulatory threshold is reached. More precisely, currently in nuclear medicine departments, the management of liquid radioactive waste requires the installation of expensive devices and the transportation and storage of radioactive materials in decay tanks.

[0005] All currently used components involve:

[0006] - Radiation protection toilets,

[0007] - Lead-sealed devices for personnel radiation protection,

[0008] - Radioactive decay tanks,

[0009] - Systems (non-selective) for managing the concentration of one or more radioactive isotopes in aqueous solutions.

[0010] Before being disposed of in nature, liquid radioactive waste is stored and transported in decay tanks.

[0011] The recent increase in the use of tracers for IVR, especially the increase in the use of 177 Lu-PSMA in metastatic prostate cancer, has led to an increased demand for 177 Lu (the radioactive isotope used in this tracer). Generally speaking, in addition to the example of prostate cancer cases, it is expected that in the coming years, the use of 177 Lu and other radioactive isotopes (β emitters, α emitters, etc.) in IVR tracers will increase.

[0012] The use of IVR in the coming years must address significant challenges associated with the increase in tracers. These challenges exemplarily correspond to:

[0013] - Generation of additional radioisotopes,

[0014] - Better control of the discharge of these radioisotopes, which are currently discharged in nature.

[0015] - Increasing logistical adaptability for patient reception.

[0016] The radioactive waste generated by patients has a half-life of less than 100 days and is subsequently discharged in nature when the radioactivity is below 10 becquerels per liter. In the case of a significant increase in the number of patients to be treated, this can lead to problems after the saturation of the radioactive tanks related to the increase in the number of treated patients.

[0017] According to current regulations, the currently known techniques enable health personnel to carry out radiation protection in accordance with current regulations before being discharged in nature. However, these techniques cannot:

[0018] - Selectively separate radioisotopes,

[0019] - Separate radioisotopes to reintegrate them into the GMP (Good Manufacturing Practice) production line,

[0020] - Create an autonomous treatment device for radioactive waste management and independent of the public radioactive collection circuit (connected radioactive tanks),

[0021] - Integrate these units into the radiopharmaceutical production circuit.

[0022] Therefore, there is currently a need for a technical solution to the problems listed above. Therefore, the present invention aims to remedy all these drawbacks.

[0023] In particular, an object of the present invention is on the one hand a more economical solution for limiting the production and storage of necessary radioisotopes, and on the other hand an environmental protection solution for limiting their pollution by avoiding discharging the said radioisotopes into nature. Another object of the present invention is to enable care units to quickly adapt to the installation requirements of protection rooms according to clinical needs. Summary of the Invention

[0024] According to the present invention, this object is achieved by means of a device for recovering at least one radioisotope of interest present in the urine of patients, said device being intended to be connected to a toilet, said device comprising a urine collector, a treatment unit, a pressure management system configured to move urine from the urine collector to the treatment unit and within the treatment unit, the treatment unit comprising:

[0025] ○At least one filtration and recovery device for each radioactive isotope of interest, comprising an ion retention element and at least one reaction solution reservoir, the filtration and recovery device being configured to filter and recover the radioactive isotope of interest,

[0026] ○A sorting module connected to the urine collector, configured to identify the radioactive isotope of interest in the collected urine and direct the collected urine to at least one filtration and recovery device corresponding to the detected radioactive isotope,

[0027] ○At least one first storage chamber, which is fluidly connected to each filtration and recovery device configured to recover the corresponding radioactive isotope.

[0028] Therefore, this solution can achieve the above object. In particular, the present invention can recover the radioactive isotopes excreted from the urine of patients. Considering the disclosed data, at 6 hours after injection, the excretion rate of Lu-PSMA is about 45%, so this recovery is significant and can address the above environmental and economic issues through the following methods:

[0029] - Reduce the production requirements of various radioactive isotopes,

[0030] - Solve the problem of long-term storage of radioactive isotopes and reduce their excretion in uncontrolled environments.

[0031] The device for recovering radioactive isotopes according to the present invention may include one or more of the following features, which may be separate from each other or combined with each other:

[0032] - The sorting module may provide a spectrometer configured to detect the radioactive isotope of interest,

[0033] - The device may include a first storage chamber for each radioactive isotope of interest,

[0034] - The suction of the patient's urine can be activated by detecting the fluid in the urine collector,

[0035] - The device may include a second storage chamber configured to recover the water element of the collected urine, the second storage chamber being fluidly connected to the sorting module and each filtration and recovery device,

[0036] - The pressure management system may be configured to generate:

[0037] ○Negative pressure in the sorting module in response to the detection of liquid in the urine collector,

[0038] ○Positive pressure in the sorting module in response to the detection of the radioactive isotope of interest,

[0039] o a negative pressure in the first storage chamber in response to the release of the reaction solution from the reservoir of the filtration and recovery device,

[0040] - the ion retaining element of the filtration and recovery device may be a cation exchange resin,

[0041] - the device may also include a feces collector,

[0042] - the device may also include a clean room,

[0043] - The clean room may comprise a separation module.

[0044] Another object of the present application relates to a method for recovering at least one radioisotope of interest present in the urine of a patient, which is implemented by the above-mentioned device. The method comprises the following steps:

[0045] - Collect urine from the patient through a urine collector,

[0046] -Suction urine to the sorting module,

[0047] - detect the radioactive isotopes of interest and direct them to the corresponding filtering and recovery devices,

[0048] - capture of the radioisotope of interest on the retention device of the filtration and recovery device,

[0049] - releasing the reaction solution so as to release the radioisotope of interest,

[0050] - transferring and storing said radioisotope of interest fluid to / in a first storage chamber. BRIEF DESCRIPTION OF THE DRAWINGS

[0051] The invention will be better understood and other objects, details, features and advantages of the invention will become more apparent by reading the following detailed description of embodiments of the invention, given by way of illustrative and non-limiting examples only, and with reference to the accompanying drawings, in which:

[0052] Figure 1 is an overall block diagram of a collecting device according to a first embodiment.

[0053] Figure 2 is an overall block diagram of a collecting device according to a second embodiment.

[0054] Figure 3 is a block diagram of a filtering and recovery device and a purification device according to the present invention. DETAILED DESCRIPTION

[0055] like Figure 1As shown, the present invention relates to a device 10 for recovering at least one radioactive isotope of interest present in a patient's urine.

[0056] The device 10 is intended to be connected to a toilet used by the patient for excretion after a medical intervention involving a radioactive isotope of interest. The device 10 is of cabinet size, preferably at most 2m 2 so as to be able to be integrated into the infrastructure of the room.

[0057] For this purpose, the device 10 according to the present invention comprises:

[0058] - a urine collector 12,

[0059] - a processing unit 14,

[0060] - a pressure management system 16, which is configured to move urine from the collector 12 to and within the processing unit 14.

[0061] The urine collector 12 is generally bowl-shaped and is suitable for both radiation-protected and non-radiation-protected toilets. The urine collector 12 is at least partially made of a non-adhesive material to eliminate all collected elements, such as Teflon.

[0062] In order to put the urine collector 12 in fluid contact with the processing unit 14, the bottom of the urine collector 12 has a valve that opens by suction.

[0063] When liquid is detected at the bottom of the urine cup 12, the pressure management system 16 triggers the suction. This detection occurs more specifically when a negative pressure of 0.5 bar to 1 bar is detected. The detection can also correspond to the presence of the patient on the toilet. This detection can specifically be obtained by a sensor on the urine collector 12. In this step, the pressure management system 16 acts as a urine suction system. This suction can prevent the stagnation of radioactive urine in the urine collector 12 outside the processing unit 14.

[0064] The flushing of the urine collector 12 is preferably automatically managed by a water distribution device. This flushing is preferably minimal and is carried out by multiple water jets to limit the amount of water added while eliminating the radioactivity that may remain in the urine collector 12.

[0065] In a series of alternative embodiments, the device has two different collectors 12, 17: a urine collector 12 and a feces collector 17. The two collectors 12, 17 are separate and suitable for installation on an existing radiation-protected toilet, that is, the toilet has a central divider with the urine collector 12 in the front and the feces collector 17 in the back.

[0066] In a first alternative embodiment, the feces collector 17 is not connected to the treatment unit 14. The feces collector 17 is in fluid connection with the second storage chamber 18.

[0067] In order to bring the feces collector 17 into fluid contact with the second storage chamber 18, the bottom of the feces collector 17 has a lid that opens by suction. The triggering of this suction is similar to that of the urine collector 12 described above. The flushing of the feces collector 17 is also similar to the flushing of the urine collector 12 described above.

[0068] The second storage chamber 18 is preferably in the form of a small radiation-shielded tank. The second storage chamber 18 includes a motorized propeller for comminuting the collected feces. The second storage chamber 18 also includes an element or product (such as lime) for stopping the fermentation of feces. It is also capable of implementing a method for liquefying the feces from the liquid discharged from the treatment unit 14 and the flushing liquid from the feces collector 17.

[0069] The urine collector 12 is connected to the treatment unit by an inlet pipe 19 that is at least partially made of radiation-shielding material. The inlet pipe 19 is configured to keep the distance between the urine collector 12 and the treatment unit 14 as short as possible. The length of the inlet pipe 19 is about one meter. This distance is as short as possible to reduce losses, avoid pipe stagnation, and limit the investment required to protect these elements from radiation.

[0070] In order to minimize the risk of biological proliferation in the treatment unit 14 and in the final product, the inlet pipe 19 includes at least one filter. Thus, the collected urine is filtered through at least one filter preferably having pores of 0.22 μm. This helps to retain uroepithelial cells, cell debris, and bacteria that are typically found in the urine of patients. This waste can be transferred to the second storage chamber 18.

[0071] The treatment unit 14 has a radiation-shielded housing such that the interior of the treatment unit for treatment is radiation-shielded. This shielding is necessary to protect patients, caregivers, and accompanying persons who have not undergone internal vector radiotherapy. This shielding enables the device 10 to be installed in any environment, especially in an environment without radiation shielding, such as a general ward.

[0072] As Figure 1 shown, the treatment unit 14 includes:

[0073] ○ At least one filtration and recovery device 20 for each radioactive isotope of interest,

[0074] ○ A sorting module 22 connected to the urine collector 12 through the inlet pipe 19 and connected to the filtration and recovery device 20,

[0075] ○At least one first storage chamber 24, which is fluidly connected to each filtration and recovery device 20 configured to recover a corresponding radioactive isotope.

[0076] Thus, the sorting module 22 is configured to identify the radioactive isotopes of interest in the collected urine and direct the collected urine to at least one filtration and recovery device 20 corresponding to the detected radioactive isotope.

[0077] It is common to define "radioactive isotope" as "radioisotope".

[0078] For this purpose, in the embodiment as Figure 1 shown, the sorting module 22 includes a sorting chamber 26 that houses a system 28 for detecting radioactive isotopes, such as a spectrometer 28. The sorting module 22 also includes a computing unit 30 connected to the detection system 28 (such as a spectrometer) and the pressure management system 16. In addition, the fluid connection between the sorting chamber 26 of the sorting module 22 and the filtration and recovery device 20 is provided by at least one anti - reflux valve 32, which is controlled by the computing unit 30 and configured to open only in response to the detection of a radioactive isotope of interest.

[0079] When the collected urine reaches the sorting chamber 26, the detection system 28 thus detects the radioactive isotopes of interest, for example, by the spectrum (γ - probe / β - probe / α - probe) of the types of isotopes with different radioactivities, for example 131 I, 177 Lu, 225 Ac, 161 Tb, 149 Tb, 67 Cu.

[0080] In any manner known to those skilled in the art, the molecules of the radioactive isotope (or isotopes) of interest are not injected into the patient alone. What is injected into the patient is an assembly of multiple molecules of the radioactive isotope of interest. This molecular assembly is commonly referred to as a "radiopharmaceutical" and abbreviated as RPD. Thus, in most cases, each RDP typically contains a carrier molecule and a radioactive isotope. By binding to a target expressing the corresponding biomarker, the RDP can study physiological processes. The radioactive isotope can trace the molecule in the patient's body and enable imaging examinations. In some special cases, the patient is directly treated by the radioactive isotope of the RDP. Therefore, this is not an imaging method but a direct treatment means. This way of binding the radioactive isotope of interest to the carrier molecule is generally referred to as internal vector radiotherapy. Chelating agents can bind the radioactive isotope to the carrier molecule. The free radioactive isotope is not bound to the carrier molecule or the chelating agent. The chelated radioactive isotope is the radioactive isotope bound by non-covalent bonds in the chelating agent.

[0081] According to the detected radioactive isotope, the calculation unit 30 drives the corresponding anti-reflux valve 32. Thus, each anti-reflux valve 32 opens on an autonomous and separate fluid return path, each forming a filtration and recovery device 20.

[0082] Each filtration and recovery device 20 includes an ion retention element 36 and at least one reagent solution reservoir 38. Each filtration and recovery device 20 is configured to filter and recover the radioactive isotope of interest detected in the sorting chamber 26. Each ion retention element 36 is preferably for single use.

[0083] Preferably, the ion retention element 36 is a cation exchange resin. This type of resin can bind all positively charged molecules / ions to the solid phase and allow neutral molecules or negatively charged molecules / ions to pass through. This type of resin must be able to withstand a wide pH range and have a high affinity for divalent and / or trivalent ions, and at the same time be able to elute them later to recover the free RDP / radioactive isotope. Macherey-Nagel TM sold PS-H + type resin can be adapted for this type of use.

[0084] Preferably, the reaction solution reservoir 38 contains a high-concentration cation solution. It must be charged regularly.

[0085] The ion retention element 36 can ensure the discharge of water and concentrate the radiopharmaceutical (RDP) and the radioactive isotopes of interest. In fact, urine consists of more than 95% water, so it is crucial to be able to discharge the excess water and concentrate the RDP / radioactive isotopes of interest. More precisely, the ion retention element 36 can capture free and chelated radioactive isotopes (RDP) (e.g., captured on a cation exchange resin). Thus, when the excess water is discharged, the RDP and radioactive isotopes are retained in the ion retention element 36. Therefore, the recovered excess water (and generally associated water elements) can be transferred to the second storage chamber 18 through the pressure management system 16.

[0086] In the case where the radioactive isotopes of interest are not contained in the collected urine, the collected urine can be directly transferred to the second storage tank 18 through the pressure management system 16.

[0087] Once the excess water is removed, the radioactive isotopes are then eluted from the reservoir 38 with a high-concentration cation solution. When the urine is circulated through the pressure management system 16, the capture of free and chelated radioactive isotopes is achieved by the ion retention element 36. The elution is also guided by the pressure management system 16. All of these are controlled by the computing unit 30.

[0088] After leaving the filtration and recovery device 20, the recovered radioactive isotopes of interest are transferred to the first storage chamber 24 dedicated to storing the radioactive isotopes of interest by driving the pressure management system 16.

[0089] Each first storage chamber 24 is adapted to sort the radioactive isotopes selected by the sorting module 22 so as not to mix them with different radioactive isotopes.

[0090] Since the ion retention element 36 of each filtration and recovery device 20 is for single use, the sorting module 22 will direct each newly collected device (plant) to a new filtration and recovery device 20 even if the radioactive isotopes of interest collected twice are the same. However, all radioactive isotopes of the same type of interest are stored in the same first storage chamber 24 until the capacity of the first storage chamber 24 is reached.

[0091] Therefore, each first storage chamber 24 is connected to at least one filtration and recovery device 20, preferably a plurality of filtration and recovery devices 20, through a pipeline having at least one mechanically automatic closing and anti-backflow valve controlled by the computing unit 30.

[0092] Each first storage chamber 24 is movable and replaceable to empty its contents. Each first storage chamber 24 can be moved in a robotic and semi-automatic manner. In this case, the device 10 further includes a motorized carriage for transferring and replacing each first storage chamber 24 without operation.

[0093] Each first storage chamber 24 preferably has a cubic shape with a side length of 40 cm to 50 cm. In a manner to protect the environment from any form of radioactivity, each first storage chamber 24 has an inner wall containing a non-adhesive material and washable in an autoclave. Each storage chamber 24 also has an outer wall made at least in part of a material that limits the diffusion of γ radiation. The thicknesses of these two walls are adapted to the emissions of each radioactive isotope of interest. Each first storage chamber 24 also has a space between its inner and outer walls that can contain plexiglass to limit the diffusion of β-radiation.

[0094] Each first storage chamber 24 is connected to the control unit 30 of the sorting module 22 and has a connected measurement system enabling it to determine in real time the accumulation of liquid or the accumulation of material.

[0095] Other radioactive isotopes not managed by the filtration and recovery device 20 can be transferred to the second storage chamber 18 through the pressure management system 16.

[0096] In summary, as Figure 2 shown, the pressure management system 16 is particularly configured to generate:

[0097] - A negative pressure in the sorting chamber 26 (and the second storage chamber 18), which responds to the detection of liquid in the urine collector 12 (and / or the feces collector 17) to transfer the collected urine (and feces) to the sorting chamber 26 (or the second storage chamber 18) (see 100 in Figure 2 .

[0098] - A positive pressure in the sorting chamber 26, which responds to the detection of the radioactive isotope of interest to transfer the collected urine to the filtration and recovery device 20 (see 200 in Figure 2 .

[0099] - A negative pressure in the first storage chamber 24, which responds to the reaction solution released from the reservoir 38 of the filtration and recovery device 20 to transfer the solution to be retained to the first storage chamber 24 (see 300 in 2).

[0100] When this system is present, the pressure management system 16 maintains a permanent negative pressure in the second storage chamber 18 to send the various wastes of the various sorting steps, filtration steps, and (depending on the embodiment) purification steps thereto as they progress.

[0101] Thus, the device 10 according to the present invention is capable of implementing a method for recovering at least one radioactive isotope of interest present in a patient's urine. The method comprises the following steps:

[0102] - collecting the patient's urine through the urine collector 12,

[0103] - sucking the urine into the sorting module 22,

[0104] - detecting the radioactive isotope of interest and directing the radioactive isotope of interest to the corresponding filtration and recovery device 20,

[0105] - capturing the radioactive isotope of interest on the retention device 36 of the filtration and recovery device 20,

[0106] - releasing the reaction solution so as to release the radioactive isotope of interest,

[0107] - fluid transferring and storing the radioactive isotope of interest into the first storage chamber 24.

[0108] In some embodiments, the processing unit 14 further comprises a purification unit 40 configured to purify the radioactive isotopes recovered by the filtration and recovery device 20. In the case where the processing unit 14 does not include the purification unit 40, the purification is carried out outside the device 10, which can be carried out at the site of collecting the patient's urine or at the processing site.

[0109] The purification unit 40 particularly comprises a chelating agent column 42, an anti-chelating agent antibody column 44 (each column is preferably for single use), a buffer solution reservoir 46 and an acid solution reservoir 48 (each reservoir must be filled regularly) for implementing the following purification method:

[0110] I. Through the chelating agent column 42 (e.g., a silica column grafted with a chelating agent of the DOTA type or DTPA type or any other chelating agent having a relative affinity for free radioactive isotopes and releasing them under easy conditions). This step is capable of recovering free radioactive isotopes in the solution, such as 177 Lu]Lu +++ 、 225 Ac]Ac +++ etc. (which are not chelated by RDP). The anti-DOTA antibody is very specific for such a chelating agent, but may potentially recognize other types of macrocyclic chelating agents having a structure similar to DOTA.

[0111] II. The flow through the column in I then passes through the column of the anti-chelating agent antibody 44 (e.g., a resin column grafted with an anti-chelating agent antibody (such as DOTA) of RDP). This step is capable of recovering the intact MRP (or at least its chelated portion containing the radioactive isotope).

[0112] III. If the device 10 includes a purification unit 40, the flow through the column in II is directly fed into the second storage chamber 18. If not, the flow through the column in II is not retained.

[0113] IV. Subsequently, the two columns in I and II are washed with a weakly acidic solution (pH 6 to 6.5) from the buffer solution reservoir 46 to enable separation of various molecules that have a non-specific interaction with the columns. If the device 10 includes a purification unit 40, this solution is directly fed into the second storage chamber 18. If not, the solution is not retained.

[0114] V. Subsequently, the two columns in I and II are treated with an acidic solution (pH 3 to 5) from the acidic solution reservoir 48 to enable separation of the free radioactive isotope (column in I) and the individuals retained on the column grafted with the chelating agent (column in II). The solution is retained and subsequently subjected to a chelating agent separation step to obtain a solution with only the free radioactive isotope.

[0115] The column presented as an example in point I is specifically designed for use with 177m Lu 177 Lu generators and has significant advantages in cases where a large amount of free radioactive isotope is found in the collected urine (due to normal separation of the chelating agent or radiolysis by DOTA).

[0116] In some embodiments, the purification chamber 40 of the device 10 further includes a separation module 50 configured to separate the radioactive isotope from the chelating agent. In the case where no separation module is provided in the purification chamber 40, the solution recovered in point V is subsequently fed into a treatment center or transferred to a separation module to effect separation between the radioactive isotopes.

[0117] The separation module 50 is capable of performing the steps of separating the radioactive isotope and the chelating agent.

[0118] This last step consists of releasing the radioactive metal from the chelating agent by acidifying the medium in which the RDP is found. In fact, in the presence of + H + ions, separation of the chelating agent / radioactive isotope may occur more readily. Combining heating of the solution with a high concentration of

[0119] H to accelerate separation of the chelating agent / radioactive isotope.

[0120] It should be noted that the separation of the chelating agent / metal is a very slow step, and one of the advantages of the present invention is to accelerate this process when the device 10 provides a purification chamber 40 including a separation module 50 to recycle most of the free radioactive isotope for new RDP labeling. Figure 3As shown, each component of the processing unit 14 is preferably connected to the second storage chamber 18 (when it is present) through a system of anti-reflux valves and fluid connections, so as to be able to discharge waste at each step of the radioactive isotope recovery process. The presence of the anti-reflux valves is crucial for ensuring that the fluid flows only in one direction, i.e., in the direction of the second storage chamber 18 (or the first storage chamber 24 in the applicable case).

[0121] In the case where a patient is simultaneously treated with multiple radioactive isotopes of interest, and the radioactive isotopes have half-lives envisioned for separation and subsequent reuse, the device 10 according to the present invention may include an isotope separation module (not shown) for implementing a separation method resulting from different radioactive isotopes of interest, which is a step of "filtration and recovery of radioactive isotopes". The separation method may consist of chromatographic separation.

[0122] Therefore, the present invention proposes an integrated solution for recovering the waste generated by patients treated by IVR, such as urine and feces. Thus, the present invention enables the re-evaluation of urine to extract various radioactive molecules and the isotopes bound thereto. In the case where most isotopes are excreted or reduced and excreted through feces, feces are collected for subsequent treatment.

[0123] Each step of the device 10 according to the present invention integrates all steps from the collection of radioactive urine to the reprocessing of radioactive isotopes to comply with good manufacturing practice (GMP) reprocessing.

Claims

1. An apparatus (10) for recovering at least one radioactive isotope of interest present in a patient's urine, the apparatus (10) being adapted to be connected to a toilet, the apparatus (10) comprising a urine collector (12), a processing unit (14), a pressure management system (16) configured to move urine from the urine collector (12) to the processing unit (14) and within the processing unit (14), the processing unit (14) comprising: ○ At least one filtration and recovery device (20) for each radioactive isotope of interest, comprising an ion retention element (36) and at least one reaction solution reservoir (38), the filtration and recovery device (20) being configured to filter and recover the radioactive isotope of interest, ○ A sorting module (22) connected to the urine collector (12), configured to identify the radioactive isotope of interest in the collected urine and direct the collected urine to at least one filtration and recovery device (20) corresponding to the detected radioactive isotope, ○ At least one first storage chamber (24) in fluid connection with each filtration and recovery device (20) configured to recover the corresponding radioactive isotope.

2. The recovery apparatus (10) according to the preceding claim, characterized in that The sorting module (22) provides a detection system (28) configured to detect the radioactive isotope of interest.

3. The recovery apparatus (10) according to any one of the preceding claims, characterized in that The device (10) includes a first storage chamber (24) for each radioactive isotope of interest.

4. The recovery apparatus (10) according to any one of the preceding claims, characterized in that The aspiration of the patient's urine is activated by detecting the liquid in the urine collector (12).

5. The recovery apparatus (10) according to any one of the preceding claims, characterized in that The device (10) includes a second storage chamber (18) configured to recover the water element of the collected urine, the second storage chamber (18) being in fluid connection with the sorting module (22) and each filtration and recovery device (20).

6. The recovery apparatus (10) according to any one of the preceding claims, characterized in that The pressure management system (16) is configured to generate: - A negative pressure in the sorting module (22) in response to the detection of liquid in the urine collector (12), - A positive pressure in the sorting module (22) in response to the detection of the radioactive isotope of interest, - A negative pressure in the first storage chamber (24) in response to the release of the reaction solution from the reservoir (38) of the filtration and recovery device (20).

7. The recovery apparatus (10) according to any one of the preceding claims, characterized in that The ion retention element (36) of the filtration and recovery device (20) is a cation exchange resin.

8. The recovery apparatus (10) according to any one of the preceding claims, characterized in that The device (10) further includes a feces collector (17).

9. The recovery apparatus (10) according to any one of the preceding claims, characterized in that The device (10) further includes a purification chamber (40).

10. A method for recovering at least one radioactive isotope of interest present in a patient's urine, which is implemented by means of the apparatus (10) according to any one of the preceding claims, characterized in that The method includes the following steps: - Collecting the patient's urine through the urine collector (12), - Aspirating the urine into the sorting module (22), - Detecting the radioactive isotope of interest and directing the radioactive isotope of interest to the corresponding filtration and recovery device (20), - Capturing the radioactive isotope of interest on the retention device (36) of the filtration and recovery device (20), - Releasing the reaction solution to release the radioactive isotope of interest, - Fluid transferring and storing the radioactive isotope of interest into / in the first storage chamber (24).

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