Abstract: A method of determining a quantity of a first radioisotope in a source term, disintegrating into a second radioisotope, the radioisotopes respectively emitting first and second gamma rays screened by the source term, the method comprising the steps: a) determining the theoretical ratio of counts between the first and second rays emitted in the absence of screening; b) measuring the net counts associated with the first and second rays emitted by the first and second radioisotopes; c) determining the screening rates of the first and second rays by the source term based on the ratio obtained in step a) and the counts obtained in step b); d) determining the quantity of the first radioisotope based on the screening rate of either the first or the second ray determined in step c).

Abstract: A frame for eyewear for protecting against ionizing radiation, comprising a frontal portion extending laterally by the two lateral protective elements, and a device for maintaining the frame on the face of a user under the conditions under which it is worn, and characterized in that the lateral protective elements are integrally formed with the frontal portion and in that the frontal portion and the lateral protective elements are made of a radio-attenuation material. Further, eyewear for protecting against ionizing radiation comprising such a frame and to an assembly comprising this eyewear and a device for distributing weight.

Abstract: A method of determining a quantity of a first radioisotope in a source term, disintegrating into a second radioisotope, the radioisotopes respectively emitting first and second gamma rays screened by the source term, the method comprising the steps: a) determining the theoretical ratio of counts between the first and second rays emitted in the absence of screening; b) measuring the net counts associated with the first and second rays emitted by the first and second radioisotopes; c) determining the screening rates of the first and second rays by the source term based on the ratio obtained in step a) and the counts obtained in step b); d) determining the quantity of the first radioisotope based on the screening rate of either the first or the second ray determined in step c).

Abstract: A device for the cyclonic separation of solid particles contained in a fluid, comprising a primary cyclone chamber, a secondary cyclone chamber, an inlet channel for fluid loaded with solid particles opening into the primary cyclone chamber, an outlet channel for fluid cleaned of the solid particles connected to the secondary cyclone chamber, and a ducting unit connecting the primary cyclone chamber to the secondary cyclone chamber and surrounded by the primary cyclone chamber. The ducting unit comprises a core delimiting the secondary cyclone chamber and having at least one helical groove having a bottom which diverges away from an axis of the secondary cyclone chamber in a direction towards the latter, and a cap covering a part of the core in such a way as to delimit, with the groove, a channel connecting the primary cyclone chamber to the secondary cyclone chamber.

Abstract: A method for measuring dosage by means of a radiation detector, especially an X-radiation or gamma-radiation detector, used in the spectroscopic mode, and a dosage measurement system using said method. A range of energies and a dose type H is chosen, a radiation detector of a given type is used, spectra measured by the detector are established for various radiations of the given type, the energies of which are within the chosen range and the respective doses of which are known, and from the spectra, a weighting function is established, that is a correspondence between a mean dose increment and a mean energy, deposited into the detector. This enables a person provided with a dosimeter identical to the detector to know at any time the mean absorbed dose rate, expressed in the amount H.

Abstract: A device for the cyclonic separation of solid particles contained in a fluid, comprising a primary cyclone chamber, a secondary cyclone chamber, an inlet channel for fluid loaded with solid particles opening into the primary cyclone chamber, an outlet channel for fluid cleaned of the solid particles connected to the secondary cyclone chamber, and a ducting unit connecting the primary cyclone chamber to the secondary cyclone chamber and surrounded by the primary cyclone chamber. The ducting unit comprises a core delimiting the secondary cyclone chamber and having at least one helical groove having a bottom which diverges away from an axis of the secondary cyclone chamber in a direction towards the latter, and a cap covering a part of the core in such a way as to delimit, with the groove, a channel connecting the primary cyclone chamber to the secondary cyclone chamber.

Abstract: A method for measuring dosage by means of a radiation detector, especially an X-radiation or gamma-radiation detector, used in the spectroscopic mode, and a dosage measurement system using said method. A range of energies and a dose type H is chosen, a radiation detector of a given type is used, spectra measured by the detector are established for various radiations of the given type, the energies of which are within the chosen range and the respective doses of which are known, and from the spectra, a weighting function is established, that is a correspondence between a mean dose increment and a mean energy, deposited into the detector. This enables a person provided with a dosimeter identical to the detector to know at any time the mean absorbed dose rate, expressed in the amount H.

Abstract: The invention relates to the use of a mixture comprising erbium and praseodymium as a radiation attenuating composition, i.e. as a composition that can attenuate ionizing radiation, in particular X- and gamma-type electromagnetic radiation. The invention also relates to a radiation attenuating material comprising an erbium- and praseodymium-based composition, as well as a protective article which provides group or individual protection against ionizing radiation and comprises said material. The invention is suitable for use in nuclear medicine (scintigraphy, radiotherapy, etc.), radiology, medical imaging, the nuclear industry, etc.

Abstract: The invention relates to the use of a mixture comprising erbium and praseodymium as a radiation attenuating composition, i.e. as a composition that can attenuate ionising radiation, in particular X- and gamma-type electromagnetic radiation. The invention also relates to a radiation attenuating material comprising an erbium- and praseodymium-based composition, as well as a protective article which provides group or individual protection against ionising radiation and comprises said material. The invention is suitable for use in nuclear medicine (scintigraphy, radiotherapy, etc.), radiology, medical imaging, the nuclear industry, etc.