Abstract: A method for quantifying intrinsic dimensions of radiation sensors, particularly ionizing radiation sensors, and a device for implementing the method. The method for quantifying the intrinsic dimensions of a radiation sensor includes: defining and modeling the sensor using a schematic diagram of the sensor, determining via numerical computation and via experimental design theory elements that affect the sensor, measuring various specific spatial positions around the sensor, via a multi-frequency calibration source of the radiation, and designing, via experimental design theory, the elements that affect a response of the sensor.

Abstract: A device for measuring an amount of beryllium in a radioactive object, including: a hollow cylinder of a first piece made of a material to thermalize neutrons emitted by the radioactive object and a metal piece to mitigate a dose rate on the radioactive object, the first piece having a hollow cylinder shape deprived of a wall fraction, the metal piece including a solid part inserted in a space which corresponds to the deprived wall fraction of the first piece and a recessed part which is an extension of the solid part and is accommodated within the wall of the first piece, in contact with the first piece; a gamma radiation source accommodated in an indentation of the recessed part of the metal piece; and at least one neutron detector placed in a bulk of the first piece.

Abstract: A method for quantifying intrinsic dimensions of radiation sensors, particularly ionizing radiation sensors, and a device for implementing the method. The method for quantifying the intrinsic dimensions of a radiation sensor includes: defining and modeling the sensor using a schematic diagram of the sensor, determining via numerical computation and via experimental design theory elements that affect the sensor, measuring various specific spatial positions around the sensor, via a multi-frequency calibration source of the radiation, and designing, via experimental design theory, the elements that affect a response of the sensor.

Abstract: A device for measuring an amount of beryllium in a radioactive object, including: a hollow cylinder of a first piece made of a material to thermalize neutrons emitted by the radioactive object and a metal piece to mitigate a dose rate on the radioactive object, the first piece having a hollow cylinder shape deprived of a wall fraction, the metal piece including a solid part inserted in a space which corresponds to the deprived wall fraction of the first piece and a recessed part which is an extension of the solid part and is accommodated within the wall of the first piece, in contact with the first piece; a gamma radiation source accommodated in an indentation of the recessed part of the metal piece; and at least one neutron detector placed in a bulk of the first piece.

Abstract: A fission chamber count rate measurement device and to the associated fission chamber calibration device; the count rate measurement device comprises: (1) a measurement cell, which contains the fission chamber (CH); (2) a neutron generator, which emits neutrons in the form of periodic pulses towards the fission chamber; (3) a neutron counter (K), which detects and counts the neutrons emitted by the neutron generator; and (4) a computing circuit, which delivers, over a predetermined time interval, a fission chamber count rate normalized with reference to the number of neutrons counted by the neutron counter (K).

Abstract: A system for in situ nuclear measurement of alpha radiation of an effluent and a related method. The system includes: M diamond semiconductor detectors obtained by chemical vapor deposition, or silicon semiconductor detectors covered with a diamond layer, as alpha radiation detectors, configured to be immersed in the effluent, and to measure alpha radiation emitted by the effluent, M is an integer greater than or equal to 1; P measuring channels connected to the M alpha radiation detectors, P is an integer greater than or equal to 1 and less than or equal to M, each of the P measuring channels configured to provide a value or a sum of alpha activity values from the M alpha radiation detectors to which they are connected; and, if P is greater than 1, a mechanism for adding together results from the P measuring channels.

Abstract: A movable device for measuring physical quantities of nuclear materials contained in a shielded cell, which device can be brought up against the shielded cell and can be retracted therefrom, the device configured to carry out the measurement in the position in which it is against the shielded cell. The device includes a carriage, a support member placed on the carriage, and a shielded container placed on the support member. The shielded container includes a transfer container configured to store the nuclear material to be measured, and an opening configured to be aligned with an opening in one wall of the shielded cell. The support member is made of graphite and includes a housing accommodating a neutron emission module, a casing covering the shielded container, the casing being made of graphite, and a neutron measurement mechanism fastened to the casing.

Abstract: A system for in situ nuclear measurement of alpha radiation of an effluent and a related method. The system includes: M diamond semiconductor detectors obtained by chemical vapour deposition, or silicon semiconductor detectors covered with a diamond layer, as alpha radiation detectors, configured to be immersed in the effluent, and to measure alpha radiation emitted by the effluent, M is an integer greater than or equal to 1; P measuring channels connected to the M alpha radiation detectors, P is an integer greater than or equal to 1 and less than or equal to M, each of the P measuring channels configured to provide a value or a sum of alpha activity values from the M alpha radiation detectors to which they are connected; and, if P is greater than 1, a mechanism for adding together results from the P measuring channels.

Abstract: A movable device for measuring physical quantities of nuclear materials contained in a shielded cell, which device can be brought up against the shielded cell and can be retracted therefrom, the device configured to carry out the measurement in the position in which it is against the shielded cell. The device includes a carriage, a support member placed on the carriage, and a shielded container placed on the support member. The shielded container includes a transfer container configured to store the nuclear material to be measured, and an opening configured to be aligned with an opening in one wall of the shielded cell. The support member is made of graphite and includes a housing accommodating a neutron emission module, a casing covering the shielded container, the casing being made of graphite, and a neutron measurement mechanism fastened to the casing.

Abstract: A fission chamber count rate measurement device and to the associated fission chamber calibration device; the count rate measurement device comprises: (1) a measurement cell, which contains the fission chamber (CH); (2) a neutron generator, which emits neutrons in the form of periodic pulses towards the fission chamber; (3) a neutron counter (K), which detects and counts the neutrons emitted by the neutron generator; and (4) a computing circuit, which delivers, over a predetermined time interval, a fission chamber count rate normalized with reference to the number of neutrons counted by the neutron counter (K).