Abstract: The present invention describes a dosimetry system for use in an irradiation system for radiology or radiotherapy. The dosimetry system comprises an at least two dimensional, radioluminescent, irradiation detection surface comprising radiosensitive material, the radiosensitive material having radioluminescent properties. The system also comprises a detection system configured for detecting radioluminescent radiation from the at least two-dimensional detection surface upon irradiation with a radiology or radiotherapy irradiating beam. The detection system comprises a detector sensitive for radioluminescence and a filter for at least partially blocking radiation from said radiology or radiotherapy irradiating beam and ambient light.

Abstract: The present invention describes a membrane mask for immobilization of a region of interest during radiation therapy. The mask comprises at least one material forming a matrix, and at least one radiation-sensitive material integrated as micro- or nano-sized material elements in or onto the matrix. The radiation-sensitive material advantageously provides the possibility of using the mask for performing dosimetry. Use of the mask and a method for performing dosimetry also are described.

Abstract: A method is described for producing nuclear fuel products, including the steps of receiving metallic or intermetallic uranium-based fuel particle cores, providing at least one physical vapour deposited coating layer surrounding the fuel particle core and embedding the nuclear fuel particles in a matrix so as to form a powder mixture of matrix material and coated fuel particles. The at least one physical vapour deposited coating layer may include inhibitors of inhibiting, stabilizing and/or reducing interaction between metallic and intermetallic uranium-based fuel particles cores and the matrix wherein the fuel particles typically may be embedded. The deposited coating layer may include neutron poisons.

Abstract: A system for measuring radiation dose comprises an excitation device adapted for directing an energy wave at a volume of a substance comprising gas-filled microparticles, a detector for detecting a response signal emitted and/or modified from the volume of the substance comprising gas-filled microparticles; and a control unit. The control unit is adapted for calculating a dose of ionizing radiation previously received by the volume of the substance based on the response signal. A method includes measuring a received dose of ionizing radiation and using a contrast agent for non-invasive in-situ dosimetry.

Abstract: A device for online measurement of a flow of fast and epithermal neutrons. The device has a fast and epithermal neutron detector (DNR) able to detect principally fast and epithermal neutrons; a thermal neutron detector (DNT) able to detect principally thermal neutrons; a first circuit (C1) for processing the signal delivered by the fast neutron detector; a second circuit (C2) for processing the signal delivered by the thermal neutron detector; a means (CE, PMM) suitable for determining the progressive sensitivity to the fast neutrons and to the thermal neutrons of each of the neutron detectors, and a computer (CALC) which computes the flow of fast and epithermal neutrons on the basis of the said progressive sensitivities and of the signals delivered by the first and second processing circuits.

Abstract: A device for online measurement of a flow of fast and epithermal neutrons. The device has a fast and epithermal neutron detector (DNR) able to detect principally fast and epithermal neutrons; a thermal neutron detector (DNT) able to detect principally thermal neutrons; a first circuit (C1) for processing the signal delivered by the fast neutron detector; a second circuit (C2) for processing the signal delivered by the thermal neutron detector; a means (CE, PMM) suitable for determining the progressive sensitivity to the fast neutrons and to the thermal neutrons of each of the neutron detectors, and a computer (CALC) which computes the flow of fast and epithermal neutrons on the basis of the said progressive sensitivities and of the signals delivered by the first and second processing circuits.