ESTIMATION OF RADIOLOGICAL EXPOSURE LEVELS IN A MINING AREA BASED ON 238U, 226Ra, 232Th and 40K ACTIVITY MEASUREMENTS: A CASE STUDY FOR BEYLIKOVA-SIVRIHISAR COMPLEX ORE SITE IN TURKEY.

The study estimated the radiological exposure levels in a mining area for miners in the Beylikova-Sivrihisar (Turkey) complex ore site containing 238U, 226Ra and 232Th. Sixty samples were collected from the study area based on a geologic map. The radionuclide activities were measured using a 78.5% efficient n-type HPGe detector. The measured mean activities were 1871 ± 38 Bq kg-1 for 238U, 1749 ± 5 Bq kg-1 for 226Ra, 3467 ± 9 Bq kg-1 for 232Th and 309 ± 2 Bq kg-1 for 40K. From the measured results, the external effective dose was calculated to be max. 3.80 ± 0.03 mSv y-1 (mean: 2.04 ± 0.03 mSv y-1) for inside gallery and max. 7.59 ± 0.05 mSv y-1 (mean: 4.08 ± 0.05 mSv y-1) for outdoor. Additionally, the external exposure index was calculated to be Hex = 33.5 ± 0.2(mean: 18.2 ± 0.3) and internal exposure index to be Hin = 45.9 ± 0.3 (mean: 22.9 ± 0.4). The results indicate that additional radiation protection measures should be taken during the mining process if an opencast mining is implemented in Beylikova complex ore deposit.

Early effect of the fear of terrorism on a hospital's emergency department use and on the incidence of cardiovascular events: A Turkish multicenter study.

BACKGROUND: To our knowledge, the early effect of the fear caused by terrorism on human health, especially its effect on the number of visits to medical emergency departments (EDs), has not yet been studied. OBJECTIVES: To observe the effect of fear from terrorist alerts on the use of EDs and on the rate of cardiovascular (CV) and/or cerebrovascular events. SETTING: In Istanbul, Turkey, there was a terror alert on the weekend of 19 and 20 March 2016. In this multicenter retrospective study, we compared the data of patients from that weekend with those from the preceding and following weekends. PATIENTS: A total of 12 324 adult patients' records were included in this study: 4562 patients in the first weekend, 3627 patients in the second, terror alert weekend, and 4135 patients in the third weekend. MEASUREMENTS: The ED, CV, and cerebrovascular incidence rates of the above three groups were compared. RESULTS: The rate of ED use was the least in the weekend of the terror alert; the highest rate occurred during the weekend prior to it (female applications decreased more [P = 0.03]). The medical center that was the farthest from the crowded central places of the city and from the place where suicide bombing occurred was less affected by the decrease in use. CONCLUSIONS: Fear associated with terrorism may affect human health indirectly by preventing patients from reaching the necessary emergency healthcare facilities. This finding may be a pathfinder to decision-makers in such extraordinary emergency conditions. Further studies are needed in this field.

Standardization of 142Pr activity concentration.

142Pr (praseodymium-142), a potential radionuclide for brachytherapy, was produced after irradiating high purity natural Pr2O3 powder in a research reactor. The irradiated powder was then dissolved in acids and diluted for measurement. Several radioactivity measurement methods were used in the standardization of 142Pr radionuclide. This work reports the results of standardization of 142Pr with CIEMAT/NIST efficiency tracing method, gamma spectrometry and a calibrated ionization chamber. The activity measured from different standardization methods are compatible with each other within the uncertainty limits. The CIEMAT/NIST efficiency tracing method gives the lowest uncertainty and is a reliable method for the standardization of this radionuclide.

Characterization of paraffin based breast tissue equivalent phantom using a CdTe detector pulse height analysis.

In this study, paraffin was selected as a base material and mixed with different amounts of CaSO4·2H2O and H3BO3 compounds in order to mimic breast tissue. Slab phantoms were produced with suitable mixture ratios of the additives in the melted paraffin. Subsequently, these were characterized in terms of first half-value layer (HVL) in the mammographic X-ray range using a pulse-height spectroscopic analysis with a CdTe detector. Irradiations were performed in the energy range of 23-35 kVp under broad beam conditions from Mo/Mo and Mo/Rh target/filter combinations. X-ray spectra were acquired with a CdTe detector without and with phantom material interposition in increments of 1 cm thickness and then evaluated to obtain the transmission data. The net integral areas of the spectra for the slabs were used to plot the transmission curves and these curves were fitted to the Archer model function. The results obtained for the slabs were compared with those of standard mammographic phantoms such as CIRS BR series phantoms and polymethylmethacrylate plates (PMMA). From the evaluated transmission curves, the mass attenuation coefficients and HVLs of some mixtures are close to those of the commercially available standard mammography phantoms. Results indicated that when a suitable proportion of H3BO3 and CaSO4·2H2O is added to the paraffin, the resulting material may be a good candidate for a breast tissue equivalent phantom.

The applicability of MGA method for depleted and natural uranium isotopic analysis in the presence of actinides (232Th, 237Np, 233Pa and 241Am).

The multi-group analysis (MGA) method for the determination of uranium isotopic abundances in depleted uranium (DU) and natural uranium (NU) samples is applied in this study. A set of non-destructive gamma-ray measurements of DU and NU samples were performed using a planar Ge detector. The relative abundances of 235U and 238U isotopes were compared with the declared values of the standards. The relative abundance for 235U obtained by MGA for a "clean" DU or NU sample with a content of uranium>1wt% is determined with an accuracy of about +/-5%. However, when several actinides such as 232Th, 237Np, 233Pa and 241Am are present along with uranium isotopes simulating "dirty" DU or NU, it has been observed that MGA method gives erroneous results. The 235U abundance results for the samples were 6-25 times higher than the declared values in the presence of above-mentioned actinides, since MGA is utilized the X-ray and gamma-ray peaks in the 80-130 keV energy region, covering XKalpha and XKbeta regions. After the least-squares fitting of the spectra, it is found that the increases in the intensities of the X-ray and gamma-ray peaks of uranium are remarkably larger in the complex 80-130 keV region. On the other hand, it is observed that the interferences of the actinide peaks are relatively less dominant in the higher gamma-ray region of 130-300 keV. The results imply the need for dirty DU and NU samples that the MGA method should utilize the higher energy gamma-rays (up to 1001 keV of (234m)Pa) combined with lower energies of the spectra, which may be collected in a two detector mode (a planar Ge and a high efficient coaxial Ge).