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 radiation dosimeter for measuring radiation dose within a region includes a structure having a scintillating material that emits light when exposed to radiation. Deformable radio-luminescent elements are located within the structure and configured to generate optical energy in response to irradiation.

A radiation dosimeter for measuring radiation dose within a region includes a structure having a scintillating material that emits light when exposed to radiation. Deformable radio-luminescent elements are located within the structure and configured to generate optical energy in response to irradiation.

Disclosed herein are a method, apparatus, and software for passive, non-destructive assay of holdup deposits in nuclear piping by in-pipe apparatus. A detector deployed within a pipe is collimated to observe radiation impinging radially inward from decay of deposits that lie on the pipe wall. A radiation detector is centered in the pipe and collimated by a pair of coaxial shielding discs disposed equidistant from the detector. This arrangement causes radiation from a truncated cylinder of pipe deposit within a field of regard to impinge on the detector, while precluding radiation emanating from pipe walls beyond the field of regard from reaching the detector. Hence, observations are unique to a known cylindrical length of pipe. The detector assembly is translated through pipes by an autonomous mobile robotic apparatus. Computer software controls the robotic apparatus, logs data, and post-processes to assay deposits.

The present invention relates generally in part to BeO-based compounds that are capable of storing at least part of the energy of incident ionizing radiation and releasing at least part of the stored energy upon optical stimulation and heating. BeO-based compounds dosimetry was also developed in instrumentation, application and fundamental investigations. The present disclosure further relates the to the investigation of a BeO-based optically stimulated luminescence (OSL) dosimeter together with an OSL reader, and discusses the design and operation of an OSL reader, suitable to measure OSL emission of BeO-based dosimeters, for example beryllium oxide doped with sodium, dysprosium and erbium. The present disclosure further relates to the use of BeO-based compounds comprising BeO and at least one dopant selected from the group consisting of sodium, dysprosium and erbium as a fiber-coupled OSL dosimeter.

The present invention relates generally in part to BeO-based compounds that are capable of storing at least part of the energy of incident ionizing radiation and releasing at least part of the stored energy upon optical stimulation and heating. BeO-based compounds dosimetry was also developed in instrumentation, application and fundamental investigations. The present disclosure further relates the to the investigation of a BeO-based optically stimulated luminescence (OSL) dosimeter together with an OSL reader, and discusses the design and operation of an OSL reader, suitable to measure OSL emission of BeO-based dosimeters, for example beryllium oxide doped with sodium, dysprosium and erbium. The present disclosure further relates to the use of BeO-based compounds comprising BeO and at least one dopant selected from the group consisting of sodium, dysprosium and erbium as a fiber-coupled OSL dosimeter.

The invention relates to a system (1) for detecting image parameters during the exposure of films (2), in particular X-ray films. It is an object of the invention to provide a system which allows a simple and fast production of optimally exposed recordings. For this purpose, the system (1) comprises a detector element (3) which can be detachably attached to a film (2) and which detects in a spatially resolved manner the radiation (4) impinging on the film (2) during exposure or the radiation (4) transmitted through the film and thereby generates a signal from which image parameters generated by the current film exposure can be derived.

The invention relates to a system (1) for detecting image parameters during the exposure of films (2), in particular X-ray films. It is an object of the invention to provide a system which allows a simple and fast production of optimally exposed recordings. For this purpose, the system (1) comprises a detector element (3) which can be detachably attached to a film (2) and which detects in a spatially resolved manner the radiation (4) impinging on the film (2) during exposure or the radiation (4) transmitted through the film and thereby generates a signal from which image parameters generated by the current film exposure can be derived.

The application relates to determining the amount of a predetermined type of radiation irradiated on a sensor material by: a) providing a sensor material; b) exposing the sensor material to the predetermined type of radiation for retaining the predetermined type of radiation in the sensor material for a predetermined period of time; c) subjecting the sensor material, which has been exposed to the predetermined type of radiation, to heat treatment and/or to optical stimulation; and d) determining the amount of visible light emitted by the sensor material as a result of being subjected to the heat treatment and/or to the optical stimulation; wherein the sensor material is represented by the following formula (I).

A method as well as a composite material for detecting free neutrons are disclosed that include a converter material, which is configured to generate in response to a capture of neutrons a secondary radiation, and a detector material, which is configured to store an information relating to the secondary radiation and to release it again in a later evaluation by optically stimulated luminance. The converter material and the detector material each are present in a plurality of particles, which are jointly present in the composite material as material mixture. In order to improve the detection of neutrons with regard to a person dosimetry, that is the estimation of a dose absorbed by a human, it is envisaged that the detector material is formed from beryllium oxide and/or the converter material is formed from lithium tetraborate.