A measuring tool (1) for measuring a delivered dose of radiation emitted by at least one electron beam emitter (2a-b) in an irradiation area (2) used to sterilise packaging material to be later formed into a package is provided. The measuring tool (1) comprises: at least one transducer (3) configured to convert a characteristic of the delivered dose of radiation to another characteristic; a frame (5) configured to hold the at least one transducer (3) and insert the at least one transducer (3) into the irradiation area (2); and at least one connector (7) configured to allow signal transfer from the at least one transducer (3) to a read-out system (9) remote of the irradiation area (2). Use of said tool and a method for calibrating a radiation dose emitted by at least one electron beam emitter (2a-b) in an irradiation area (2) used to sterilise packaging material to be later formed into a package are also provided.

What is described and claimed is a dosimeter for measuring a radiation dose of ionizing radiation comprising a measurement chamber and a light sensor, wherein the measurement chamber is filled with a fluorophore and is lightproof, such that no light from the surroundings can be incident in the measurement chamber, and wherein the light sensor is configured to detect fluorescent light generated by ionizing radiation in the fluorophore in the measurement chamber and to generate a signal that is proportional to the fluence of the detected fluorescent light. Furthermore, the use of such a dosimeter, and a spectrometer comprising a plurality of such dosimeters are presented and claimed.

The present disclosure relates to a method of measuring an absorbed dose of radiation in small irradiation fields. The method of measuring an absorbed dose of radiation in small irradiation fields, includes an acquisition step of acquiring absorbed dose distribution data of radiation; a determination step of determining a region where an absorbed dose of radiation of a predetermined ratio or more is absorbed based on the absorbed dose distribution data of radiation; a formation step of forming a scintillator having a shape in which a plurality of hexahedral cells are coupled to have a shape matching the region; a measurement step of measuring a absorbed dose of radiation irradiating the scintillator from a radiation irradiation device; and a calculation step of calculating the absorbed dose of radiation of the cell at a predetermined position by using predetermined Equations.

This dosimeter comprises: a transducer material capable, when it is excited by a secondary ionizing radiation, of generating photons or electric charges, an amplifying layer capable, in response to its excitation by the primary ionizing radiation, of generating the secondary ionizing radiation.

This amplifying layer comprises a first and a second amplifying sublayer stacked on top of one another. The first and the second amplifying sublayers are composed of at least 70%, by weight, respectively, of at least one first and one second material, the atomic numbers of which are greater than or equal to 29. The atomic number of the first material being less than the atomic number of the second material. The first sublayer is interposed between the second sublayer and the transducer material.

A method is provided for determining the dose rate {dot over (H)} of nuclear radiation field, namely a gamma radiation field, with a radiation detection system (RDS), comprising a scintillator, a photodetector, an amplifier and a pulse measurement electronics. The pulse measurement electronics includes a sampling analog to digital converter, where the nuclear radiation deposes at least some of its energy in the scintillator, thereby producing excited states in the scintillation material, with the excited states decaying thereafter under emission of photons with a decay time τ. Photons are absorbed by the photodetector under emission of electrons, those electrons forming a current pulse, said current pulse being amplified so that the resulting current signal can be processed further in order to determine the charge of the pulse measured.

The invention provides a detection system for ionizing radiation, a method of manufacturing a detection system for ionizing radiation, a method of detecting ionizing radiation, a detection chamber for detecting ionizing radiation by liquid scintillation counting, and a method of detecting ionizing radiation by liquid scintillation counting. The detection system for ionizing radiation comprises a detector with a detection surface. The detector is configured to detect ionizing radiation that is incident on the detection surface. An adsorption layer is provided on said detection surface, the adsorption layer being configured to bind target particles, wherein the target particles are radioactive atoms or molecules.

Techniques are disclosed for systems and methods to provide a radiation detector module for a radiation detector. A radiation detector module includes a metallic and/or metalized enclosure, a radiation sensor disposed within the enclosure, readout electronics configured to provide radiation detection event signals corresponding to incident ionizing radiation in the radiation sensor, and a cap including an internal interface configured to couple to the readout electronics and an external interface configured to couple to a radiation detector, where the cap is configured to hermetically seal the radiation sensor within the enclosure. The cap may be implemented as an edge plated printed circuit board (PCB) including a slot configured to mate with a planar edge of an open surface of the enclosure, where the slot is soldered to the planar edge of the enclosure to hermetically seal the radiation sensor within the enclosure.

A radiation monitoring device 1 includes a scintillator portion 10 which emits light whose intensity depends on a dose of incident radiation, an optical fiber 20 which transmits photons generated in the scintillator portion 10, a photoelectric converter 30 which converts photons transmitted by the optical fiber 20 to electric signals, a signal counter 40 which counts each of electric signals after being converted by the photoelectric converter 30 with a certain dead time adjusted relative to time width of an irradiation pulse of radiation, a dose calculation unit 50 which calculates a dose from a signal count value counted by the signal counter 40, and a display unit 60 which displays a result of measurement calculated by the dose calculation unit 50.

Proposed is an apparatus for verifying a radiation dose using a patient-specific tumor-shaped scintillator including a probe adapter to which a 3D tumor-shaped scintillator having a guide is attached; a receiving portion to which the probe adapter is detachably coupled; a light guide which extends from the receiving portion and includes optical fiber transmitting visible light generated by irradiating radiation in the 3D tumor-shaped scintillator; a photomultiplier tube converting the visible light transmitted from the light guide into an electric signal and amplifying the converted electric signal; and a current electrometer measuring an output current by inputting the electric signal of the photomultiplier tube.

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.