Abstract: A protection device to be fitted onto a syringe (2) used for injecting radioactive material(s). The radiation protection device includes a tubular radiation protection housing (1) that includes an outer tubular part (15), which constitutes at least a portion of the outer surface (11) thereof, and which is made of an elastomeric material. The tubular portion (15) also includes an annular constrictive portion (20) including a resiliently deformable inner surface that is used to apply a compressive force around the cylindrical body (3) of the inserted syringe (2).

Abstract: A sterile screen cover made of radioprotective material has an L-shaped horizontal section, including a front wall associated with a side wall. The front wall has two orifices through which the arms of the operator can pass, a first orifice being located close to the angle of the screen, the second being located on the free edge of the front wall. The sterile cover is a single part that includes at least one internal “panel” and one “external panel” joined together by a joining region, the panels intended to cover, respectively, at least the internal and external faces of the front wall and at least part of the height of its free edge. The joining region has an indentation shaped to match the border of the second passage orifice; these inner and outer panels are each provided with an opening intended to be placed in front of the first passage orifice.

Abstract: A medical unit includes a shielded enclosure (2) in which are accommodated:—elements (13) for supporting a container (12) including a source or a generator of injectable radioactive product (11),—elements (10) for supporting a syringe (6),—a device (3) of the activimeter type, and—a system of pipes (9, 20, 23, 24) associated with at least one valve (15). The syringe support (10), the valve (15) and the radioactive source support (13) are arranged vertically relative to one another, respectively from top to bottom, the syringe support (10) being arranged to support the syringe (6) with the plunger (8) thereof oriented upward. The valve (15) and the syringe plunger (8) can be operated so as to ensure the withdrawal, dilution and injection operations.

Abstract: A container for transporting a receptacle (2) containing a radioactive substance for medical use. includes a shielded body made up of a belt of side walls connected to a base element and defining a top opening, and a shielded closing lid attachable to the top opening by locking elements shaped so as to be activated by a translational movement of the lid in the top opening, this “locking movement” taking place along the axis of the opening and towards the opposing base element. The lid is further equipped with elements for deactivating the locking elements to enable it to be separated from the container body. In one advantageous embodiment, the lid has a plurality of retractable projecting studs designed to fit by a snap-action type phenomenon into at least one complementary housing formed in the opening of the container body during the locking movement.

Abstract: The present invention relates to a sterile cover intended for covering a screen (1) made of radioprotective material, of the type having an L-shaped horizontal section, comprising a front wall (2) associated with a side wall (3), which front wall (2) is provided with two orifices (10, 11) through which the arms of the operator can pass, a first orifice (10) being located close to the angle of said screen, the second (11) being located on the free edge (13) of said front wall (2).

Abstract: A container for transporting a receptacle (2) containing a radioactive substance for medical use. includes a shielded body made up of a belt of side walls connected to a base element and defining a top opening, and a shielded closing lid attachable to the top opening by locking elements shaped so as to be activated by a translational movement of the lid in the top opening, this “locking movement” taking place along the axis of the opening and towards the opposing base element. The lid is further equipped with elements for deactivating the locking elements to enable it to be separated from the container body. In one advantageous embodiment, the lid has a plurality of retractable projecting studs designed to fit by a snap-action type phenomenon into at least one complementary housing formed in the opening of the container body during the locking movement.

Abstract: A medical unit includes a shielded enclosure (2) in which are accommodated:—elements (13) for supporting a container (12) including a source or a generator of injectable radioactive product (11),—elements (10) for supporting a syringe (6),—a device (3) of the activimeter type, and—a system of pipes (9, 20, 23, 24) associated with at least one valve (15). The syringe support (10), the valve (15) and the radioactive source support (13) are arranged vertically relative to one another, respectively from top to bottom, the syringe support (10) being arranged to support the syringe (6) with the plunger (8) thereof oriented upward. The valve (15) and the syringe plunger (8) can be operated so as to ensure the withdrawal, dilution and injection operations.

Abstract: A syringe protecting device includes a casing (9) made of a material protecting against radiation, adapted to cover the syringe cylindrical body (3), which casing (9) is associated with a structure (10) likewise made of a material protecting against radiation, designed to form at least a partial protective shield on the rear end of the syringe, while allowing the syringe plunger (4) to be operated. In one particular embodiment, the protective shield is globally shaped like a cylindrical sleeve (10) provided with a base (18); the sleeve (10) is mounted sliding on the protective casing (9) by capping it through its rear end, and it comprises mechanism (20) for being removably secured to the stem (5) operating the syringe plunger (4).

Abstract: A method of measuring the activity of a radioisotope (3) placed in an ionisation chamber (1) consists in:—determining the energy spectrum of the radiation emitted by the radioisotope;—automatically comparing the energy spectrum with a set of pre-recorded or pre-programmed radioisotope energy spectra in such a way as to identify the radioisotope present;—subsequently, automatically directing the calibration coefficient corresponding to the radioisotope present to the electronic measuring elements in order to obtain the appropriate activity measurement. The invention provides a totally automatic activity measurement. Moreover, the invention also relates to an activity meter with radioisotope recognition which is used to obtain an automatic activity measurement. The device employs one or more scintillation—or semi-conductor-type radiation detectors (10) for determining the energy spectrum of the radioisotope present.

Abstract: A protective screen includes a front wall (1), connected to a lateral wall (2) running perpendicular or essentially perpendicular to the front wall (1), the walls (1, 2) including transparent panels (8, 10) over at least a part of the height thereof. The upper part (8) of the front wall (1) is inclined forwards, forming an overhang which permits the operator to approach the working region and with two holes (11, 12) to permit the passage of the operator's arms.

Abstract: A protective screen includes a front wall (1), connected to a lateral wall (2) running perpendicular or essentially perpendicular to the front wall (1), the walls (1, 2) including transparent panels (8, 10) over at least a part of the height thereof. The upper part (8) of the front wall (1) is inclined forwards, forming an overhang which permits the operator to approach the working region and with two holes (11, 12) to permit the passage of the operator's arms.

Abstract: According to the invention, the method of measuring the activity of a radioisotope (3) placed in an ionisation chamber (1) consists in:—determining the energy spectrum of the radiation emitted by the radioisotope;—automatically comparing said energy spectrum with a set of pre-recorded or pre-programmed radioisotope energy spectra in such a way as to identify the radioisotope present;—subsequently, automatically directing the calibration coefficient corresponding to the radioisotope present to the electronic measuring means in order to obtain the appropriate activity measurement. The invention provides a totally automatic activity measurement. Moreover, the invention also relates to an activity meter with radioisotope recognition which is used to obtain an automatic activity measurement. Said device employs one or more scintillation- or semi-conductor-type radiation detectors (10) for determining the energy spectrum of the radioisotope present.

Abstract: Novel radiation attenuating material made of plastic material comprising a metallic filler consisting of a combination of at least two, preferably, three metals or metal derivatives (oxides or alloys) of different type, except lead, selected on the basis of discontinuities of the X- or gamma radiation absorption curve of the metals or metal derivatives, so as to obtain complementarity of the curves on the energy range of radiation to be absorbed or attenuated, to optimise radiation protection on the energy range. The metallic filler is preferably in the form of a powder whereof the particle dimensions are for the major part less than 50 &mgr;m. The filler is present in proportions ranging between 70 and 95% of the weight of the final material and is selected preferably among dense metals such as tungsten, tin, bismuth, barium, antimony, lanthanides, tantalum or derivatives thereof, in particular oxides and alloys.

Abstract: A syringe protecting device includes a casing (9) made of a material protecting against radiation, adapted to cover the syringe cylindrical body (3), which casing (9) is associated with a structure (10) likewise made of a material protecting against radiation, designed to form at least a partial protective shield on the rear end of the syringe, while allowing the syringe plunger (4) to be operated. In one particular embodiment, the protective shield is globally shaped like a cylindrical sleeve (10) provided with a base (18); the sleeve (10) is mounted sliding on the protective casing (9) by capping it through its rear end, and it comprises mechanism (20) for being removably secured to the stem (5) operating the syringe plunger (4).