Device for recovering medical radioactive isotopes

Abstract

The present invention relates to a device (10) for recovering a radioactive isotope of interest present in the urine of a patient, intended to be connected to a toilet. The device includes a urine collector (12), a treatment unit (14) and a pressure management system (16). The treatment unit (14) comprises: a filtration and recovery device (20) for each radioactive isotope of interest 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 towards the filtration and recovery device (20) corresponding to the detected radioactive isotope, at least one primary storage chamber (24) in fluid connection with the filtration and recovery device (20) configured to recover the corresponding radioactive isotope.

Description

MEDICAL RADIOACTIVE ISOTOPE RECOVERY DEVICE FIELD OF THE INVENTION

[0001] The present invention relates to devices which enable the recovery of radioactive isotopes from biological fluids. STATE OF THE ART

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

[0003] More specifically, vectorized internal radiotherapy (VIR) is the therapeutic branch of nuclear medicine. Its development has been rapid in recent years, particularly in the context of the management of metastatic prostate cancer by so-called " 177 Lu-PSMA » targeting PSMA, prostate-specific membrane antigens (PSMA) expressed by cancer cells.

[0004] During treatment with RIV, in particular by177 Lu-PSMA, the majority of the treatment is injected and eliminated through urine. In the current state of the art, this radioactivity is subsequently stored and then eliminated into the environment when the regulatory threshold is reached. More specifically, currently in nuclear medicine departments, the management of liquid radioactive waste requires the installation of expensive furniture and logistics with transport and storage of radioactivity in decay tanks.

[0005] The set of elements currently used concerns: radioprotected toilets, leaded devices allowing the radioprotection of personnel, radioactive decay tanks, systems for managing concentrations of radioactive isotope(s) in aqueous solutions (non-selective).

[0006] Before being disposed of in nature, liquid radioactive waste is stored and transported to decay tanks.

[0007] The recent increase in indications for the use of IVR, particularly in metastatic prostate cancer with the 177 Lu-PSMA, leads to an increased need for production of 177 Lu (radioactive isotope used for this indication). Generally speaking, and beyond the example of prostate cancer cases, projections envisage an increase in indications for IVF in the coming years with the 177 Read but also with other radioactive isotopes (P, a, etc. emitters).

[0008] The use of RIV in the coming years must respond to major challenges linked to the increase in indications. These challenges correspond schematically to: an increasing production of radioactive isotopes, better control of the elimination of these radioactive isotopes, currently eliminated in nature. Logistical adaptability allowing an increasing reception of patients.

[0009] Radioactive waste generated by the patient has a half-life of less than 100 days and is then disposed of in the environment when the radioactivity is less than 10 becquerels per liter. This can lead to problems with the saturation of radioactive tanks due to the increasing number of patients being treated in the event of a significant increase in the number of patients.

[0010] Currently known techniques allow for radiation protection of healthcare personnel before disposal in nature, in compliance with current regulations. However, these techniques do not allow: selective isolation of radioactive isotopes, isolation of radioactive isotopes for their reintegration into a GMP (good manufacturing practices) production route, the creation of autonomous therapeutic units for their management of radioactive waste and independent of a common radioactivity collection circuit (connected radioactive tank). the integration of these units into a radiopharmaceutical drug production circuit.

[0011] There is therefore a need today for a technical solution to the list of problems cited above. The present invention thus seeks to remedy all these shortcomings.

[0012] The present invention aims in particular to propose, on the one hand, a more economical solution making it possible to limit both the production and storage of the necessary radioactive isotopes and, on the other hand, an environmental protection solution making it possible to limit pollution by avoiding the release of said radioactive isotopes into nature. The present invention also aims to offer care units the possibility of quickly adapting the need for the installation of a protected room to the clinical need. SUMMARY

[0013] This objective is achieved, in accordance with the invention, by means of a device for recovering at least one radioactive isotope of interest present in the urine of a patient, the device being intended to be connected to a toilet, the device comprising a urine collector, a processing unit, a pressure management system configured to move the urine from the urine collector to and within the processing unit, the processing unit comprising: o at least one filtration and recovery device specific to each radioactive isotope of interest, comprising an ion retention element and at least one reactive solution reservoir, the filtration and recovery device being configured to filter and recover the radioactive isotope of interest, o a sorting module connected to the urine collector configured to identify the radioactive isotope of interest in the collected urine and direct the urine collected towards F at least one filtration and recovery device corresponding to the detected radioactive isotope, o at least one primary storage chamber in fluid connection with each filtration and recovery device configured to recover the corresponding radioactive isotope.

[0014] Thus, this solution makes it possible to achieve the aforementioned objective. In particular, this innovation allows the recycling of radioactive isotopes eliminated through the urine of patients. Knowing that the published data make it possible to estimate an elimination of Lu-PSMA at approximately 45% at 6 hours after the injection, this recovery is therefore significant and makes it possible to respond to the environmental and economic problems mentioned above by: a reduction in the production needs of the different radioactive isotopes, a solution for the prolonged storage of radioactive isotopes as well as a reduction in their elimination in an uncontrolled environment.

[0015] The radioactive isotope recovery device according to the invention may comprise one or more of the following features, taken in isolation from each other or in combination with each other: the sorting module may be provided with a spectrometer configured to detect the radioactive isotope of interest, the device may comprise a primary storage chamber for each radioactive isotope of interest, the suction of the patient's urine may be activated by detection of liquid in the urine collector, the device may comprise a secondary storage chamber configured to recover aqueous elements from the collected urine, said secondary storage chamber being in fluid connection with the sorting module and each filtration and recovery device, the pressure management system may be configured to generate: o a negative pressure in the sorting module in response to the detection of liquid in the urine collector, o a positive pressure in the sorting module in response to the detection of the radioactive isotope of interest. o a negative pressure in the primary storage chamber in response to a release of the reactive solution from the reservoir of the filtration and recovery device, the ion retention element of the filtration and recovery device may be a cation exchange resin, the device may also include a stool collector, the device may also include a purification chamber, the purification chamber may include a dissociation module.

[0016] Another subject of the present application relates to a method for recovering at least one radioactive isotope of interest present in the urine of a patient, implemented by means of the device as described above. The method comprises the following steps: collecting the patient's urine by means of the urine collector, suctioning the urine towards the sorting module, detecting the radioactive isotope of interest and the radioactive isotope of interest towards a corresponding filtration and recovery device, trapping the radioactive isotope of interest on the retention device of the filtration and recovery device, releasing the reactive solution so as to release the radioactive isotope of interest, fluidic transfer and storage of said radioactive isotope of interest towards the primary storage chamber. BRIEF DESCRIPTION OF THE FIGURES

[0017] The invention will be better understood, and other aims, details, characteristics and advantages thereof will appear more clearly on reading the detailed explanatory description which follows, of embodiments of the invention given as purely illustrative and non-limiting examples, with reference to the appended schematic drawings. In these drawings: Figure 1 is a general functional diagram of the collection device according to a first embodiment. Figure 2 is a general functional diagram of the collection device according to a second embodiment. Figure 3 is a block diagram of a filtration and recovery device and a purification device according to the present invention. DETAILED DESCRIPTION

[0018] As seen in Figure 1, the present invention relates to a device 10 for recovering at least one radioactive isotope of interest present in the urine of a patient.

[0019] The device 10 is intended to be connected to a toilet on which the patient sits to relieve himself, after a medical procedure involving a radioactive isotope of interest. The device 10 has the proportions of a cabinet, preferably of a maximum of 2m 2 , so that it can be integrated into the infrastructure of a room

[0020] The device 10 according to the present invention comprises, for this purpose: a urine collector 12, a treatment unit 14, a pressure management system 16 configured to move the urine from the collector 12 to and within the treatment unit 14.

[0021] The urine collector 12 has a general bowl shape that can be adapted to a radio-protected and non-radio-protected toilet. The urine collector 12 is at least partially made of a low-adhesive material that allows the elimination of all the collected elements, such as, for example, Teflon.

[0022] In order to place the urine collector 12 in fluid contact with the treatment unit 14, the bottom of the urine collector 12 has a valve that opens by suction.

[0023] This suction is triggered by the pressure management system 16, upon detection of liquid in the bottom of the urine collector 12. This detection is done more particularly by the detection of a negative pressure between 0.5 and Ibar. The detection can also correspond to the presence of the patient on the toilet. This detection is made possible in particular by the presence of sensors on the urine collector 12. At this stage, the pressure management system 16 plays the role of a urine suction system. This suction makes it possible to avoid the stagnation of radioactive urine in the urine collector 12 outside the treatment unit 14.

[0024] The rinsing of the urine collector 12 is preferably managed automatically by a water distribution device. This rinsing is preferably minimal and is carried out by several splashes of water in order to limit the quantity of water added while eliminating any possible residual radioactivity in the urine collector 12.

[0025] In a series of alternative embodiments, the device has two different collectors 12, 17: the urine collector 12 and a stool collector 17. The two collectors 12, 17 are separate and fit on existing radiation-protected toilets, i.e. the toilet has a central divider with the urine collector 12 in front and the stool collector 17 in the back.

[0026] In a first alternative embodiment, the stool collector 17 is not connected to the processing unit 14. The stool collector 17 is in fluid connection with a secondary storage chamber 18.

[0027] In order to bring the stool collector 17 into fluid contact with the secondary storage chamber 18, the bottom of the stool collector 17 has a valve that opens by suction. This suction is triggered in a similar manner to that described above for the urine collector 12. The rinsing of the stool collector 17 is also similar to that of the urine collector 12 described above.

[0028] The secondary storage chamber 18 is preferably in the form of a radio-protected mini-tank. The secondary storage chamber 18 comprises a motorized propeller allowing the grinding of the collected stools. The secondary storage chamber 18 also comprises an element or a product allowing the fermentation of stools (e.g. lime). It also allows the implementation of a process for liquefying stools from liquids eliminated by the treatment unit 14 and a rinsing liquid from the stool collector 17.

[0029] The urine collector 12 is connected to the treatment unit by an inlet pipe 19 made at least partially of a radioprotective material. This inlet pipe 19 is configured to make the distance traveled by the urine between the urine collector 12 and the treatment unit 14 as short as possible. This inlet pipe 19 has a length of the order of a meter. This distance is as short as possible to reduce losses, avoid stagnation in the piping and limit the investment necessary to radioprotect these elements.

[0030] In order to minimize the risks of biological development in the treatment unit 14 as well as in the final product, the inlet pipe 19 comprises at least one filter. Thus, the collected urine is filtered on at least one filter preferably having pores of 0.22 pm. This makes it possible to retain the cells of the urinary epithelium, the cellular debris as well as the bacteria typically present in the urine of a patient. This waste can be transferred to the secondary storage chamber 18.

[0031] The treatment unit 14 has a radioprotective outer casing, so that the interior of the treatment unit is radioprotected for treatment. This protection is necessary to protect both patients who have not been treated by vectorized internal radiotherapy, caregivers and accompanying persons. This protection allows the device 10 to be installed in any environment, in particular a non-radioprotected environment such as a normal hospital room.

[0032] As visible in Figure 1, the treatment unit 14 comprises: o at least one filtration and recovery device 20 specific to each radioactive isotope of interest, o a sorting module 22 connected to the urine collector 12 by the inlet pipe 19 and connected to the filtration and recovery device 20, o at least one primary storage chamber 24 in fluid connection with each filtration and recovery device 20 configured to recover the corresponding radioactive isotope.

[0033] The sorting module 22 is thus configured to identify the radioactive isotope of interest in the collected urine and direct the collected urine towards at least one filtration and recovery device 20 corresponding to the detected radioactive isotope.

[0034] It is common to refer to a "radioactive isotope" as "radioisotopes".

[0035] For this purpose, in the embodiment shown in Figure 1, the sorting module 22 comprises a sorting chamber 26 housing a detection system 28 for the radioactive isotope, for example a spectrometer 28. The sorting module 22 also comprises a computing unit 30 connected to the detection system 28 (for example, a spectrometer) and to the pressure management system 16. The fluid connection between the sorting chamber 26 of the sorting module 22 and the filtration and recovery device 20 is, moreover, ensured by at least one non-reflux valve 32, controlled by the computing unit 30 and configured to open only in response to the detection of the radioactive isotope of interest.

[0036] Upon arrival of the collected urine in the sorting chamber 26, the radioactive isotope of interest is thus detected by the detection system 28, for example by spectrometry (gamma / beta / alpha probe) of the type of radioisotope with differentiation, for example 131 I,177 READ, 225 AC, 161 Tb, 149 Tb, 67 Cu.

[0037] As is known to anyone skilled in the art, radioactive isotope molecules (or radioisotopes) of interest are not injected alone into patients. What is injected into patients is an assembly of several molecules including the radioisotope of interest. This assembly of molecules is classically called a "radiopharmaceutical drug" and is abbreviated MRP. Thus, each MRP classically comprises, in the majority of cases, a vector molecule and a radioactive isotope. By binding to targets expressing a corresponding biomarker, the MRP makes it possible to study a physiological process. The radioactive isotope makes it possible to track this molecule in the patient and allows imaging tests to be carried out. In certain specific cases, patients are treated directly with the radioactive isotope of the MRP. This is not a case of of an imaging method but of a treatment method, directly. This way of binding the radioactive isotope of interest to a carrier molecule is classically called vectorized internal radiotherapy. A chelator allows the radioactive isotope to be attached to the carrier molecule. A free radioisotope is not attached to the carrier molecule or to the chelator. The chelated radioisotope is a radioactive isotope attached by non-covalent bonds in the chelator.

[0038] Depending on the radioactive isotope detected, the computing unit 30 actuates the corresponding anti-reflux valve 32. Each anti-reflux valve 32 thus opens onto an autonomous and isolated fluid circuit, each forming a filtration and recovery device 20.

[0039] Each filtration and recovery device 20 comprises an ion retention element 36 and at least one reactive 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 single-use.

[0040] Preferably, the ion retention element 36 is a cation exchange resin. This type of resin allows all positively charged molecules / ions to be attached to the solid phase and allows neutral molecules or negatively charged molecules / ions to pass through. This type of resin must withstand a wide pH range and must have a high affinity for divalent and / or trivalent ions while allowing their subsequent elution to recover the free MRP / radioisotope. Resins of the Chromafix® PS-H type +marketed by the company Macherey-Nagel™ could be adapted to this type of use.

[0041] Preferably, the reagent solution reservoir 38 contains a high concentration cationic solution. It must be recharged regularly.

[0042] This ion retention element 36 ensures the elimination of water and concentrates the radiopharmaceutical drug (RPD) and the radioactive isotope of interest. Indeed, urine is composed of more than 95% water, it is therefore critical to be able to eliminate excess water and concentrate the RPD / radioactive isotope of interest. More Specifically, the ion retention element 36 allows the trapping of free and chelated radioisotopes (MRP) (e.g. on a cation exchange resin). The MRP and radioisotopes are thus retained in the ion retention element 36 while the excess water is evacuated. The excess water (and generally the associated aqueous elements) thus recovered can be transferred, by the pressure management system 16, to the secondary storage chamber 18.

[0043] In the event that the collected urine does not contain a radioactive isotope of interest, the collected urine may be transferred, by the pressure management system 16, directly into the secondary storage tank 18.

[0044] Once the excess water has been removed, the radioisotopes are then eluted with the high concentration cationic solution from reservoir 38. The trapping of free and chelated radioisotopes occurs when the urine is circulated, by the pressure management system 16, through the ion retention element 36. The elution is also directed by the pressure management system 16. All of this is controlled by the computing unit 30.

[0045] At the outlet of the filtration and recovery device 20, the recovered radioactive isotope of interest is transferred, by the actuation of the pressure management system 16, to the primary storage chamber 24 dedicated to the storage of the radioactive isotope of interest.

[0046] Each primary storage chamber 24 is adapted to the radioactive isotope selected by the sorting module 22 so as not to mix it with different radioisotopes.

[0047] Since the ion retention element 36 of each filtration and recovery device 20 is single-use, the sorting module 22 directs each new plant collected to a new filtration and recovery device 20, even if the radioactive isotope of interest is the same between two collections. However, all radioactive isotopes of interest of the same type are stored in the same primary storage chamber 24. Within the capacity of said primary storage chamber 24.

[0048] Each primary storage chamber 24 is thus connected to at least one, preferably several, filtration and recovery devices 20 by a pipe with at least one anti-reflux valve and automatic mechanized closure controlled by the calculation unit 30.

[0049] Each primary storage chamber 24 is removable and replaceable for emptying its contents. Each primary storage chamber 24 can be removable robotically and semi-automatically. In this case, the device 10 further comprises a motorized trolley allowing the transfer and changing of each primary storage chamber 24 without handling.

[0050] Each primary storage chamber 24 preferably has a cube shape with a side length ranging from 40 to 50 cm. In order to protect the environment from any form of radioactivity, each primary storage chamber 24 has an inner wall comprising a low-adherence material that can be cleaned in an autoclave. Each storage chamber 24 also has an outer wall at least partially made of a material that limits the diffusion of gamma radiation. The thickness of these two walls is adapted to the emissions of each radioactive isotope of interest. Each primary storage chamber 24 also has a space between its inner wall and its outer wall, this space being able to contain plexiglass so as to limit the diffusion of B- radiation.

[0051] Each primary storage chamber 24 is connected to the control unit 30 of the sorting module 22 and has a connected gauge system allowing the quantity of liquid or material accumulated to be known in real time.

[0052] The other radioisotopes not managed by the filtration and recovery device 20 can be transferred, by the pressure management system 16 to the secondary storage chamber 18.

[0053] To summarize, as illustrated in Figure 2, the pressure management system 16 is notably configured to generate: a negative pressure in the sorting chamber 26 (and the secondary storage chamber 18) in response to the detection of liquid in the urine collector 12 (and / or the stool collector 17) in order to transfer the collected urine (and stool) to the sorting chamber 26 (or the secondary storage chamber 18) (see reference 100 in FIG. 2), a positive pressure in the sorting chamber 26 in response to the detection of the radioactive isotope of interest, in order to transfer the collected urine to the filtration and recovery device 20 (see reference 200 in FIG. 2), a negative pressure in the primary storage chamber 24 in response to a release of the reactive solution from the reservoir 38 of the filtration and recovery device 20, in order to transfer the solutions to be stored to the primary storage chamber 24 (see reference 300 in FIG. 2).

[0054] When this is present, the pressure management system 16 maintains a permanent negative pressure in the secondary storage chamber 18 in order to send there, gradually, the various waste from the different stages of sorting, filtering and (depending on the embodiments) purification.

[0055] The device 10 according to the present invention therefore allows the implementation of a method for recovering at least one radioactive isotope of interest present in the urine of a patient. The method comprises the following steps: collecting the patient's urine by means of the urine collector 12, suctioning the urine towards the sorting module 22, detecting the radioactive isotope of interest and the radioactive isotope of interest towards a corresponding filtration and recovery device 20, trapping the radioactive isotope of interest on the retention device 36 filtration and recovery device 20, releasing the reactive solution so as to release the radioactive isotope of interest, fluidic transfer and storage of said radioactive isotope of interest towards the primary storage chamber 24.

[0056] In certain embodiments, the treatment unit 14 further comprises a purification unit 40 configured to purify the radioisotopes recovered by the filtration and recovery device 20. In cases where the treatment unit 14 does not comprise a purification unit 40, the purification takes place outside the device 10, either at the patient's urine collection site or at a packaging site.

[0057] The purification unit 40 comprises in particular a column of chelators 42, a column of anti-chelator antibodies 44 (each column preferably being for single use), a buffer solution reservoir 46, an acid solution reservoir 48 (each reservoir having to be filled regularly) allowing the implementation of a purification method as described below: I. Passage through the chelating column 42 (for example a silica column grafted with DOTA or DTPA type chelators, or any other chelator having a relative affinity for free radioisotopes and allowing their release under easy conditions). This step allows the recovery of free radioisotopes in 177 +++ 225 +++ solution, such as, for example [ Lu]Lu , [ Ac]Ac , etc. (which are not chelated by the MRP). Anti-DOTA antibodies are quite specific for this chelator but can potentially recognize other types of macrocyclic chelators structurally similar to DOTA. II. The "flow through" from the column to I. is then passed onto the column of anti-chelating antibodies 44 (for example a resin column grafted with anti-chelating antibodies of the MRP (DOTA...)). This step makes it possible to recover intact MRPs (or at least their chelating part containing the radioisotope). III. If the device 10 comprises a purification unit 40, the flow through from the column to II is sent directly into the secondary storage chamber 18. If not, the flow through from the column to II is not retained. IV. The two columns in I. and II are subsequently washed with a weakly acidic solution (pH 6-6.5) from the buffer solution reservoir 46 in order to allow the detachment of the various molecules having non-specific interactions with the columns. If the device 10 includes a purification unit 40, it is sent directly to the secondary storage chamber 18. If not, this solution is not stored. V. The two columns at I. and II are subsequently treated with an acid solution (pH 3-5) from the acid solution reservoir 48 in order to allow the free radioisotopes (column at I) and the entities retained on the column grafted with the chelator (column at II) to be detached. This solution is kept and will then be subjected to the dissociation steps of the chelator to find a solution of free radioisotopes only.

[0058] The column presented as an example in point I is designed specifically for the use of Lu generators from Lu and has an important advantage in the case where a large quantity of free radioisotopes are found in the collected urine (due to normal dissociation of the chelator or via radiolysis of DOTA.

[0059] In some embodiments, the purification chamber 40 of the device 10 further comprises a dissociation module 50 configured to dissociate the radioisotope from the chelator. The solution recovered at point V is then either sent to a treatment center in cases where the purification chamber 40 is not equipped with the dissociation module, or transferred to the dissociation module to allow dissociation between radioisotopes.

[0060] The dissociation module 50 allows the implementation of a dissociation step of the radioisotope and the chelator.

[0061] This last step consists of forcing the radiometal out of the chelator by acidifying the medium in which the MRP is located. Indeed, in the presence of H ions + , the chelator / radioisotope dissociation can be done more easily. It is associated with the heating of the highly concentrated H solution +to accelerate the dissociation of chelator / radioisotope.

[0062] It should be noted that the chelator / metal dissociation is a very slow step and one of the advantages of the present invention, when the device 10 is provided with a purification chamber 40 comprising a dissociation module 50, is to accelerate this process in order to reuse a large part of the free radioisotope for new MRP labelings.

[0063] As visible in Figure 3, each element of the treatment unit 14 is preferably connected, by a system of anti-reflux valves and fluid connections, to the secondary storage chamber 18 (when this is present) in order to be able to evacuate the waste at each stage of the radioisotope recovery process. The presence of non-reflux valves is important to ensure that fluids flow in only one direction, towards the secondary storage chamber 18 (or the primary storage chamber 24, if applicable).

[0064] In the context of a patient treated simultaneously with several radioisotopes of interest having a half-time allowing for separation and subsequent reuse, the device 10 according to the present invention could comprise an isotope separation module (not shown) allowing the implementation of a separation process at the end of the different radioactive isotopes of interest from the steps of “filtration and recovery of radioactive isotopes”. This separation process could consist of a chromatographic separation.

[0065] The present invention thus presents an integrated solution for recovering waste produced by patients injected with RIV treatments such as urine and stool. Thus, the present invention allows the revalorization of urine to extract the different radioactive molecules and their attached isotopes. The stools are collected for further processing in the case of isotopes mainly evacuated by the stools or decay and elimination.

[0066] The various stages of the device 10 according to the present invention integrate all the stages ranging from the collection of radioactive urine to the reconditioning of the radioisotope for good manufacturing practice (GMP) reconditioning.

Claims

CLAIMS Device (10) for recovering at least one radioactive isotope of interest present in the urine of a patient, the device (10) being intended to be connected to a toilet, the device (10) comprising a urine collector (12), a treatment unit (14), a pressure management system (16) configured to move the urine from the urine collector (12) to and within the treatment unit (14), the treatment unit (14) comprising: o at least one filtration and recovery device (20) specific to each radioactive isotope of interest, comprising an ion retention element (36) and at least one reservoir (38) of reactive solution, the filtration and recovery device (20) being configured to filter and recover the radioactive isotope of interest,o 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, o at least one primary storage chamber (24) in fluid connection with each filtration and recovery device (20) configured to recover the corresponding radioactive isotope. Recovery device (10) according to the preceding claim, characterized in that the sorting module (22) is provided with a detection system (28) configured to detect the radioactive isotope of interest. Recovery device (10) according to any one of the preceding claims, characterized in that the device (10) comprises a primary storage chamber (24) for each radioactive isotope of interest. Recovery device (10) according to any one of the preceding claims,characterized in that the suction of the patient's urine is activated by detection of liquid in the urine collector (12)., 5. Recovery device (10) according to any one of the preceding claims, characterized in that the device (10) comprises a secondary storage chamber (18) configured to recover aqueous elements from the collected urine, said secondary storage chamber (18) being in fluid connection with the sorting module (22) and each filtration and recovery device (20).

6. Recovery device 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 primary storage chamber (24) in response to a release of the reactive solution from the reservoir (38) of the filtration and recovery device (20).

7. Recovery device (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. Recovery device (10) according to any one of the preceding claims, characterized in that the device (10) also comprises a stool collector (17).

9. Recovery device (10) according to any one of the preceding claims, characterized in that the device (10) also comprises a purification chamber (40).

10. Method for recovering at least one radioactive isotope of interest present in the urine of a patient implemented by means of the device (10) according to any one of the preceding claims, characterized in that the method comprises the following steps: collection of the patient's urine by means of the urine collector (12), suction of the urine towards the sorting module (22), detection of the radioactive isotope of interest and of the radioactive isotope of interest towards a corresponding filtration and recovery device (20), trapping of the radioactive isotope of interest on the retention device (36) of the filtration and recovery device (20), release of the reactive solution so as to release the radioactive isotope of interest, fluidic transfer and storage of said radioactive isotope of interest towards the primary storage chamber (24).

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