Description of modular devices for the measurement of external dosimetry in radiation protection.

In 2002 the Group of Radiation Dosimetry and Calibration of the Belgian Nuclear Research Centre (SCK•CEN) has developed an experimental device based on the optically stimulated luminescence (OSL) working with Al2O3:C detectors (TLD-500 and Luxel) stimulated with an argon laser. A set of devices made from different modules have been developed to permit external dosimetry measurements with thermoluminescence (TL) and OSL techniques under different conditions. This study describes these measurement devices that can be made with these modules and some of the characteristics of the different systems.

Monte Carlo calculations applied to the parametrical studies in a whole body counter.

The use of a Monte Carlo code for the analysis and interpretation of whole body counting measurements is described. The sources of error are analysed and commented to show how a counting geometry can be improved by improving accuracy and precision in a measurement. The effects of body size, contamination distribution and counting geometry are also parameters which can be easily used to improve the quality of a body burden assessment.

The reduction of limits of detection in in vivo counting of low-energy photon emitters by optimising the shape and size of detectors.

This paper compares three ways to reduce the detection limits of in vivo measurements by using passive techniques: the use of shielded rooms, the use of underground laboratories and the adjustment of the detector's dimensions to the examined energy. This study indicates that the efficiency of the detector is not the critical parameter for achieving sensitive measurements in the low-energy range and is secondary to optimisation of the background level. However, reduction of the background has a limited impact on the sensitivity of counting due to 40K in the body.

Application of Monte Carlo calculations to calibration of anthropomorphic phantoms used for activity assessment of actinides in lungs.

This paper reports on a new utility for development of computational phantoms for Monte Carlo calculations and data analysis for in vivo measurements of radionuclides deposited in tissues. The individual parameters of each worker can be acquired for an exact geometric representation of his or her anatomy, which is particularly important for low-energy gamma ray emitting sources such as thorium, uranium, plutonium and other actinides. The software discussed here enables automatic creation of an MCNP input data file based on computed tomography (CT) scanning data.

The in vivo assessment of thorium body burden by gamma ray sepctrometry.

Thorium is used in many different industrial technologies and is widely found in nature. Internal contamination with thorium is considered as highly hazardous because of its radiological and chemical toxicities, which depend on the chemical form in which thorium appears. The assessment of the thorium body burden is then of primary importance in detecting the risks of personal contamination, and for appropriate counteractions when contamination is detected.