Ionizing radiation is widely used in medical practice for both diagnostic and therapeutic purposes. However, they are not devoid of adverse health effects on exposed operators. Therefore, we propose to assess the radiological risk of the interventional radiology team of the International Polyclinic of Indénié of Abidjan during the procedures of Embolization of uterine fibromyomas. The effective and equivalent doses to the extremities and crystals were estimated by TLD dosimeters positioned at different body areas selected on the basis of a radiological analysis of the exposure of personnel during five procedures. The analysis of fluoroscopic and record times showed variability in or an average fluoroscopy time of 32.37 min with extremes of 25.14 to 56.32 min; average record time of 0.52 min with extremes of 0.12 min to 1 min. The annual effective doses were respectively, 4.04 mSv, 3.42 mSv, 2.84 mSv; 2.28 mSv, in the Radiologist (R), Operator Assistant (O2); Anesthesiologist (A2), Manipulator (M2). The annual equivalent doses to the radiologist's predominant extremities and lenses were left index and left lens with values of 37.07 mSv and 9.46 mSv. The estimated doses in our study are reassuring from a regulatory point of view of dose limits. The results of our work have shown no significant short-term danger to the health of personnel.

The objective of this work is to check the dosimetric performances of the TLD-100 as stated by the manufacturer as well as the technical standards of radiation protection. The purpose of the performance audit is to assess the inhomogeneity of TLD sensitivity, repeatability and reproducibility, linearity, energy dependence, angular dependence, and fading. All tests were performed under the conditions of ambient temperature and relative humidity recommended by the manufacturer. We began the study by calibrating the Harshaw 6600 Plus, and checking its performance. The TLD-100 performance verification results were all acceptable and in accordance with the manufacturer's advertised values and the radiation protection technical standards. However the performance of the TLD-100 that we have evaluated may have some limitations; these limits, which are sources of uncertainty, have been taken into account in this work by evaluating the overall uncertainty of the Hp (10) dose in the uncertainty range 9.45% to 15.80% by simple formulas. The TLD-100 personal dosimeters and the 6600 Plus reader system indicate that the calculated values of the overall uncertainty Hp (10) are well below the allowable values of 21% to 42% suggested for personal dosimetry services. The obtained data encourage the use of the system for the routine evaluation of the external exposure of workers under ionizing radiation in our laboratory.

Cement is the most used material in bulding activities in Côte d'Ivoire. Thus, most of the radiation exposure from the building materials is due to the cement. This work is part of radiation protection logic and therefore to assess the level of exposure due to the cement used in Côte d'Ivoire. In this study, samples of grey and white cement whose are sold on Ivorian territory were examined. To carry out this study, we analyzed these samples using a gamma spectrometer. This consisted mainly of a scintillation detector NaI (Tl) and an acquisition system both designed by the German group-LD Didactic. The specific activity of radionuclides that are 226Ra, 232Th and 40K were evaluated. The average values obtained are 29.66 Bq / kg for 226 Ra; 34.88 Bq / kg for the 232Th; 178.424 Bq / kg for 40K. These are all lower than the limit values recommended by UNSCEAR. In order to assess the radiological impact of these activities, we estimated the external and internal exposure risk indices and the annual gonadals equivalent dose. The values obtained for these parameters are well below those recommended by UNSCEAR for internal and external exposure indices, and below the world average (except for CG3 sample) for the annual gonadals equivalent dose. These results suggest that the risk to the use of these different cement brands is low.

Radioactivity is a natural phenomenon present in the universe. So, because of human life solidarity with a habitat, we are permanently in contact, especially through building materials. The objective of this work is the determination of the used cement radioactivity level in the buildings in Côte d'Ivoire. Thus, samples of grey and white cement currently used on Ivorian territory were taken. In order to determine the radioactivity level of this cement, samples were analyzed by using gamma spectrometry chain which contains a NaI (Tl) scintillation detector designed by the German manufacturer LD-DIDACTIC, coupled to a multichannel analyzer (AMC) using a Cassy Lab software. Thus, the specific activity of the primordial radionuclides 226 Ra, 232 Th and 40 K, was able to be determined. The average values obtained are 29.66 Bq/kg, 34.88 Bq/kg and 178.424 Bq/kg respectively for 226 Ra, 232 Th and 40 K. All average values are below the limit values recommended by UNSCEAR. However, we evaluated the radiological parameters such as the equivalent radium activity and the annual effective dose in order to translate the specific activity in terms of harmfulness. Values obtained for these parameters are below those recommended by ICRP and UNSCEAR. These results show that the risk incurred by the use of these different brands of cement is low.