[en] The general requirements for accreditation by NAMAS are laid down in the NAMAS Accreditation Standard, M10, and NAMAS Regulations, M11. These requirements apply to all types of measurement but in certain instances it is necessary to provide guidance on how these requirements are to be interpreted for specific types of measurements. This document has been prepared by the Radiological Working Group of the NAMAS Health and Hygiene Technical Committee in collaboration with the Health and Safety Executive to provide guidance to laboratories providing personal dosimetry services. This document details the specific requirements for personal dosimetry services using thermoluminescent (TL) dosemeters for assessing the radiation dose from: (a) Beta-rays; (b) Gamma-rays; (c) X-rays; and (d) Thermal neutrons. The aim of a personal TL dosimetry service is to issue and assess TL dosemeters and to notify the client of the doses accurately, reliably and quickly. (author)

[en] The purpose was to provide applied and research dosimetrists with sufficient information to evaluate the status and direction of their programs relative to the latest guidelines and techniques. A technical program was presented concerning experience, requirements, and advances in gamma, beta, and neutron personnel dosimetry

[en] An investigation concerning synthetic diamonds' thermoluminescent response to different LET radiations has been carried out using alpha, beta and gamma radioactive sources. The fluence interval studied with alpha radiation runs from 10⁵ to 10⁹ particles.mm^-2. Gamma irradiation covers the dose interval from 0.005 to 200 Gy and beta irradiation, from 0.1 to 160 Gy. Dose response curves, f(D), are presented. The response to alpha radiation is sub-linear in the complete interval studied while response to beta and gamma radiation shows linear-sub-linear behaviour, sub-linearity starting around 5 Gy. (Author)

[en] Materials grouped to three main issues: normative, metrological and technical support of dosimetric and radiometric control; biological dosimetry and markers of radiation effects; monitoring and reconstruction of radiation doses at radiation accidents

No abstract available

[en] The characteristics of CR-39 detectors have been investigated intensively during the last years in many laboratories. The enlargement of tracks by electrochemical etching made counting easier but, on the other hand, complicated the etching process. For routine application of CR-39 in neutron personal dosimetry neither etching nor reading should be complicated or time consuming. Recently NE-Technology (formerly: Vinten) introduced an automatic reader for chemically etched CR-39 detectors. Along with this reader a new CR-39 Material, PN3, was made available. This system would allow for a routine application of CR-39. The characteristics of PN3 detectors and possible batch constructions were investigated. (author)

[en] The Dosimetry Applications Research (DOSAR) group at Oak Ridge National Laboratory has established a national and international program for dosimetry testing and intercomparison. Under this program there have been twenty-two nuclear accident dosimeter intercomparisons conducted with a frequency of about one each a year. The primary tool used in these studies as well as in a wide variety of biological experiments, personnel training programs, and other nuclear and radiation related work has been the Health Physics Research Reactor. Currently the availability of the reactor is uncertain, and it is desirable to have alternate reliable radiation sources to continue an increasing workload. An important part of the research done at DOSAR involves calibrating several different types of equipment with known sources traceable to the National Bureau of Standards (NBS). These calibrations, although done with sufficient accuracy using available sources, were conducted in a casual manner and often resulted in undesirable exposures to the researchers and posed a general inconvenience to the smooth operation of the facility. Although extensive laboratory space and storage was available at the facility, there were no facilities for a permanent irradiation setup that could house all the neutron, gamma, and beta sources necessary

[en] A complex personal dosimeter has recently been designed that includes a gamma- and beta-ray dosimeter block and a neutron dosimeter block. These two blocks are enclosed in a badge type case so that a person can secure the dosimeter on his clothing. The gamma- and beta-ray dosimeter block consists of four thermoluminescent elements in combination with plastic filters of different thicknesses. The neutron dosimeter block consists of four thermoluminescent elements in combination with cadmium and tin filters. This complex dosimeter can individually measure or estimate the radiation doses such as gamma-rays, beta-rays, thermal neutrons, epithermal neutrons, and fast neutrons over a wide range of doses, and can also obtain information on the energy of the radiation

[en] For 10 years now the Commission of the European Communities has cooperated with the national institutes on the organization of intercomparisons in the field of personal dosimetry. One of the tasks of a group of personal dosimetry experts, made up of technical specialists from all the Member States of the European Community, is to draw up the rules in accordance with which this intercomparison programme must be carried out. The programme follows two main avenues: comparison of the institutes responsible for assessing the doses received by workers; joint study of dosimetry principles and behavior of the various measurement principles under the same irradiation conditions. Several comparisons have been made using photon dosimeters and neutron dosimeters. Thermoluminescent dosimeters have been studied jointly. An analysis has been carried out of the behavior of various dosimeters irradiated by monochromatic rays between 10 and 300 keV and rays of 9 MeV. An account will be given of the origins of these programme, its development, results and the conclusions drawn so far, and a brief outline will be given of the work to be done in future

[en] At the Centre d'etudes nucleaires, Grenoble, the Radiation Measurement Laboratory, which forms part of the Environmental Protection and Research Department, serves the entire Centre for purposes of dosimetry and the calibration of dose meters. The needs of radiation protection are such that one must have facilities for checking periodically the calibration of radiation-monitoring instruments and developing special dosimetry techniques. It was thought a good idea to arrange for the dosimetry and radiation protection team to assist other groups working at the Centre - in particular, the staff of the biology and radiobiology laboratories - and also bodies outside the framework of the French Commissariat a l'energie atomique. Thus, technical collaboration has been established with, for example, Grenoble's Centre hospitalier universitaire (university clinic), which makes use of the facilities and skills available at the Radiation Measurement Laboratory for solving special dosimetry problems. With the Laboratory's facilities it is possible to calibrate dose meters for gamma, beta and neutron measurements