Abstract: A measurement core for measuring nuclear heating, the core extending in a longitudinal direction and having a main plane, includes at least: a first layer of material, forming a first sample; a first thin layer of electrical insulation on the first sample; a thin conductive layer forming a heating electrical resistor on the first layer of electrical insulation; and a second thin layer of electrical insulation on the heating electrical resistor. A calorimetric sensor includes: an outer jacket; a gas contained in the jacket; a measurement core disposed in the jacket; a link for holding the core in the jacket and transferring the heat between the core and the jacket; and temperature measurement capable of measuring the temperature at a hot point, and the temperature at a cold point.

Abstract: A sample holder for the measurement of nuclear heating in a nuclear reactor, comprises: a body configured to contain a heat-sensitive sample along a longitudinal axis; and means for removing heat from the body to the exterior of the sample holder, wherein the means for removing heat from the body to the exterior of the sample holder comprise: a peripheral structure located on the periphery of the body; and a central structure mechanically linking the body and the peripheral structure, the central linking structure being configured to transfer heat radially, i.e. perpendicularly to the longitudinal axis, between the body and the peripheral structure. A calorimeter cell for the measurement of nuclear heating in a nuclear reactor, comprises: at least one sample holder; a seal-tight casing in which the sample holder is placed; and temperature-measuring means.

Abstract: A method for producing a device for detecting flux of neutrons with parameters in predetermined ranges, including: one phase of determining parameters, including: simulating penetration of a flux of incident neutrons with parameters in the predetermined ranges through a modelled stack including in succession and in order at least: one first electrode; one substrate including: a first layer; and a second layer; and one second electrode; and simulating at least one defect peak created in the first layer by vacancies and/or ionization of the particles generated by collisions between neutrons of the flux of incident neutrons and atoms of the second dopant species; and identifying depth of the defect peak closest the interface between the first and second layers of the modelled stack.

Abstract: A sample holder for the measurement of nuclear heating in a nuclear reactor, comprises: a body configured to contain a heat-sensitive sample along a longitudinal axis; and means for removing heat from the body to the exterior of the sample holder, wherein the means for removing heat from the body to the exterior of the sample holder comprise: a peripheral structure located on the periphery of the body; and a central structure mechanically linking the body and the peripheral structure, the central linking structure being configured to transfer heat radially, i.e. perpendicularly to the longitudinal axis, between the body and the peripheral structure. A calorimeter cell for the measurement of nuclear heating in a nuclear reactor, comprises: at least one sample holder; a seal-tight casing in which the sample holder is placed; and temperature-measuring means.

Abstract: A method for producing a device for detecting flux of neutrons with parameters in predetermined ranges, including: one phase of determining parameters, including: simulating penetration of a flux of incident neutrons with parameters in the predetermined ranges through a modelled stack including in succession and in order at least: one first electrode; one substrate including: a first layer; and a second layer; and one second electrode; and simulating at least one defect peak created in the first layer by vacancies and/or ionization of the particles generated by collisions between neutrons of the flux of incident neutrons and atoms of the second dopant species; and identifying depth of the defect peak closest the interface between the first and second layers of the modelled stack.

Abstract: A method for determining the spectral and spatial distribution of a braking photon flow along at least one direction in space (x, y, z), characterized in that the method comprises measuring the neutrons resulting from the impact of the braking photons (ph) on at least one conversion target which is moved in the direction (x, y, z) in space. The invention can be used for X-rays, medical imaging, tomography, etc.

Abstract: A method for determining the spectral and spatial distribution of a braking photon flow along at least one direction in space (x, y, z), characterised in that the method comprises measuring the neutrons resulting from the impact of the braking photons (ph) on at least one conversion target which is moved in the direction (x, y, z) in space. The invention can be used for X-rays, medical imaging, tomography, etc.

Abstract: The system for automatic determination of the density of an object (100) comprises: an apparatus (2) to determine a significant dimension (x) of said object (100), an apparatus (30) to determine the intensity (I) of a photon beam attenuated by passing through said object (100), an acquisition, processing and analysis apparatus (200), means (70, 72, 80, 82, 84, 86, 88) of transporting the object (100), first means (74, 76, 78) of adjusting the position of the object (100), second means (90, 92, 94, 96, 98) of adjusting the position of the object (100). The method for using the system described above includes steps to calibrate components of apparatuses 2 and 30, and steps to actually determine the significant dimension of objects (100), that are done on each object (100) in said set of objects.

Abstract: The system for automatic determination of the density of an object (100) comprises: an apparatus (2) to determine a significant dimension (x) of said object (100), an apparatus (30) to determine the intensity (I) of a photon beam attenuated by passing through said object (100), an acquisition, processing and analysis apparatus (200), means (70, 72, 80, 82, 84, 86, 88) of transporting the object (100), first means (74, 76, 78) of adjusting the position of the object (100), second means (90, 92, 94, 96, 98) of adjusting the position of the object (100). The method for using the system described above includes steps to calibrate components of apparatuses 2 and 30, and steps to actually determine the significant dimension of objects (100), that are done on each object (100) in said set of objects.

Abstract: According to the invention, an object (2) and particularly a radioactive waste package that may contain fissile isotopes and/or fertile isotopes, is analyzed by irradiating the object by thermal, epithermal and fast neutrons resulting from a series of initial fast neutron pulses, the prompt and delayed neutron signals emitted by the object after each pulse are measured, these signals are accumulated, and the contribution Sp of prompt neutrons originating form thermal fission and the contribution Sr of delayed neutrons originating from thermal, epithermal and fast fission are determined from this sum of all signals, and the quantity of each isotope is determined using Sp and Sr and additional information about the isotope quantites.

Abstract: According to the invention, an object (2) and particularly a radioactive waste package that may contain fissile isotopes and/or fertile isotopes, is analyzed by irradiating the object by thermal, epithermal and fast neutrons resulting from a series of initial fast neutron pulses, the prompt and delayed neutron signals emitted by the object after each pulse are measured, these signals are accumulated, and the contribution Sp of prompt neutrons originating from thermal fission and the contribution Sr of delayed neutrons originating from thermal, epithermal and fast fission are determined from this sum of all signals, and the quantity of each isotope is determined using Sp and Sr and additional information about the isotope quantities.

Abstract: A counting enclosure (24) for neutron detection has an outer wall and an inner space for receiving an object (26) to be tested, the wall being constituted by a first, inner cadmium coating (32), an inner moderator coating (38), an intermediate cadmium coating (34), an outer moderator coating (40) and an outer cadmium coating (36).