Abstract: In a radiation dose reading apparatus for a fluorescent glass element which was exposed to ionizing radiation and which is subjected to ultraviolet light radiation so as to cause fluorescence with an intensity depending on the radiation dose received by the glass element wherein the radiation dose is determined from the intensity of the fluorescence emitted from the glass elements detecting face, a fluorescence diaphragm arrangement is provided so as to overlay the glass element detecting face and is movable thereon for changing the fluorescence detecting areas and a fluorescence intensity reading device is provided for determining fluorescence intensity distribution and the glass element detecting face.

Abstract: A fluorescent glass dosimeter comprises a glass element holder including inner and outer envelopes. Each of the inner and outer envelopes has a mask frame used for covering the peripheral portions of the corresponding fluorescent detection surface of a fluorescent glass element. The fluorescent glass dosimeter further comprises upper and lower cases. The upper case serves as a pivotable lock member and includes a lock portion, the locking condition of which can be released by means of a magnet. The lower case is adapted to receive the glass element holder. The upper and lower cases are engageable with each other at their slide portions. The glass element holder includes an integral index plate havig an identification hole code at a predetermined location. A direction regulating member is provided for the lower case, and a portion engageable with the direction regulating member is provided for the glass element holder.

Abstract: A radiation dose measuring system using fluorescent dosemeters comprises fluorescent dosemeters including fluorescent glass elements having a fluorescent detection surface, a magazine capable of holding a predetermined number of fluorescent dosemeters, a magazine conveying device for conveying a magazine of a plurality of magazines fed one by one such that is predetermined segment is located to a take-out position, a fluorescent dosemeter take-out device for taking the fluorescent dosemeter from the magazine located in a predetermined position, a fluorescent glass element setting device for moving the fluorescent glass element to a predetermined measuring position and a dose measuring device for subjecting the fluorescent glass element which is set to a measuring position to an ultraviolet ray and for measuring an intensity of fluorescent light which is emitted from an excited glass element.

Abstract: An apparatus for measuring dose equivalent, absorbed dose and neutron fluence in stray radiation fields of neutron source. The apparatus includes a moderator sphere having an outer surface and a neutron detector disposed in the center of the moderator sphere for producing a counting rate representing a measure of thermal neutrons in the center of the sphere. In addition, at least one detector combination is disposed at the outer surface of the moderator sphere. The detector combination includes a plurality of neutron detectors and a shield for providing each respective detector in the plurality of detectors with a different shielding absorption of thermal neutrons. The detectors of the detector combination produce count rates which can be used to separately measure albedo neutrons back-scattered by the moderator sphere and incident thermal neutrons from the stray radiation field.

Abstract: Albedo dosimeter encapsulation for measuring neutron and gamma radiation in at least two dosimeter zones, comprises a casing having cadmium or boron containing walls which have neutron absorbing capability. The casing has a front side which faces a radiation field and a rear side which faces a body which carries the encapsulation. The rear side of the casing is closed by a cadmium or boron containing rear wall having a first portion and a second portion. A cover is located at the front side of the casing and has a cadmium or boron containing wall portion and a window portion. The casing has a first zone for holding a first dosimeter means and a second zone for holding a second dosimeter means. The first zone is aligned with the cadmium or boron containing wall portion of the cover and the first portion of the rear wall. The second zone is aligned with the window portion of the cover and the second portion of the rear wall.

Abstract: In a passive dosimeter for the detection of radon and/or thoron and their daughters and including a diffusion chamber having two end faces, a first radioactive decay detector composed of a nuclear track detector foil or an integrating .alpha.-detector sealing one end face of the chamber, and a filter transmissive for radon and/or thoron, whereby the detector provides an indication of radon and thoron decay and the resultant daughters, there is further provided a second chamber corresponding in structure to the diffusion chamber and having two end faces, with one end face of the second chamber being sealed by the side of the filter directed away from the diffusion chamber, and a second radioactive decay detector substantially identical to the first detector sealing the other end face of the second chamber, with passages being provided between the second chamber and the environment of the dosimeter for passage of gas with radon and thoron and daughters to be measured into the second chamber.

Abstract: A device for evaluating the exposure of a phosphate glass dosimeter to ioing radiation by effecting differential scanning of the dosimeter glass with light radiation, including a member for holding the glass stationary, a device for supplying a single beam of light for effecting the evaluation; and a scanning system composed of an element defining a pivotal, elongated slit, two rotatable mirrors and two stationary mirrors arranged in the path of the single beam and operable for causing the beam to scan the glass selectively along any one of three coordinates.

Abstract: A method is provided for determining the dose value of neutrons leaving a body as thermal and intermediate neutrons after having been scattered in the body. A first dose value of thermal and intermediate neutrons are detected on the surface of the body by means of a first detector for neutrons which is shielded against thermal and intermediate neutrons not emerging from the body. A second detector is used to measure a second dose value of the thermal and intermediate neutrons not emerging from the body. A first correction factor based on the first and second values is obtained from a calibration diagram and is applied to the first dose value to determine a first corrected first dose value.