[en] The atmospheric surveillance self-propelling device of the Saclay Nuclear Research Center can, by its conception (autonomy, rapid put into service, multiplicity of sampling and measurements), be used for all kind of measuring campains: pollution radioactive or not, routine or accidental situation, technical and logistic support and as a coordination or investigation vehicle

No abstract available

[en] The monitor comprises, among other things, a standing platform for the person to be tested, with an open-worked foot board. The supporting cross-pieces have a triangular cross section, the base of which faces the detector, and the point of which faces the shoesole; thereby a considerable augmentation of the detection probability is obtained. (HP)

[en] The contamination monitoring is done by means of flat detectors, which are part of two detector walls. The detector walls are interlocked at an angle of 104⁰. Both the detector walls or columns have a vertical subdivision, which reduces the sensitivity of the arrangement at these places and therefore achieves an even measurement over the measurement cross section of the person to be monitored. (DG)

No abstract available

[en] The monitor has detector devices at an angle to each other made as a rigid component which can be rotated around a vertical axis in the angle between the joined detector devices. A reset drive which can be tensioned is provided at the axis of rotation. If it is in its rest position, a platform is situated as floor plate with a foot detector between the vertical detector devices. (orig./HP)

[en] The monitor has only two detector columns at an angle to one another and possibly divided in height, whose detectors are divided in the vertical direction in a middle range depending on a reference shape. The units formed by the subdivision equal the effect produced by the subdivision in approximation to the reference shape in evaluation. By including the detector columns divided into several detectors in height, a detector of about half the width is produced at a level above the threshold. Underarm boxes are provided at the outer edge of this detector, which are directed obliquely upwards. (orig./HP)

[en] Fuji Electric is working to develop methods for utilizing and monitoring radioactivity. In the monitoring field, Fuji Electric is developing and providing personal dose monitoring systems, survey meters and the like for use at newly constructed nuclear power plants and at an increasing number of worksites that use radiation. As personal dose monitoring systems, Fuji Electric provides a dose monitoring system capable of wireless real-time monitoring of doses detected with a semiconductor-based personal dosimeter, and a body surface monitor for use when entering or existing a radiation controlled area. Additionally, using a survey meter to measure the environmental radiation surrounding a radiation handling facility, and then sharing that data with local governments and disclosing it to the public, Fuji Electric also provides systems and survey meters for realizing safety and security for the local population. (author)

[en] Among all the components required for radiation protection optimization, the evaluation of instrumentation is essential. The instrumentation in radiation protection allows to make the surveillance of personnel, installations and environment against the risk bound to radioactive contamination and ionizing radiations. The different devices can give the following functions: ambient dosimetry, (individual and environmental dosimetry), measurement of surface contaminations, air contamination by aerosols or gas, water contamination by liquid wastes,detection of criticality accidents, measurement of samples radioactivity. (N.C.)

[en] There is a need for a personal dosimeter to measure the dose equivalent of newtrons from thermal to 15MeV. The authors have developed a combination dosimeter, which consists of TLD albedo dosimeter, newtron track film (NTA), and CR-39 carbonate track-etch dosimeter, for the purpose of evaluating wide energy range newtron dose-equivalent. This paper involves following: (1) The unfolding method of evaluating the dose-equivalent from measured data of the dosimeter using SAND-2 code. (2) The basic characteristics of the developed dosimeter when irradiated by ²⁴¹Am-Be source or TRIGA-2 nuclear reacter. (3) The comparison between evaluated dose-equivalent of the dosimeter and STUDVIK remcounter evaluated value. (4) The accuracy and sensitivity of this dosimeter. The next results are obtained: (1) The developed unfolding method is enough to evaluate wide energy dose-equivalent. (2) The measured spectrum and dose-equivalent is agreed with the BF₃ bonner counter evaluated one. (3) The accuracy is estimated within +-20%, and the sensitivity is enough satisfied the standard level of NRC and ANSI. (author)