Radiological evaluation of the use of clay brick and pumice brick as a structural building material

PubMedID: 30196249In this study, clay brick (CBRICK) and pumice brick (PBRICK) samples used as structural material in the construction of dwellings, schools, workplaces and factories in Turkey were compared with each other from a radiological viewpoint. The activity concentrations of 226Ra, 232Th and 40K naturally occurring in CBRICK and PBRICK samples collected from different regions of Turkey were determined by using a gamma-ray spectrometer with a high purity germanium detector (HPGe). The average activity concentrations of 226Ra, 232Th and 40K in CBRICK and PBRICK samples were found as 35.4 ± 3.3, 37.5 ± 2.4 and 593.7 ± 42.7 Bq kg-1 and 81.9 ± 2.5, 65.8 ± 6.0 and 1066.0 ± 46.6 Bq kg-1, respectively. The radon surface exhalation rate (EXS) and radon mass exhalation rate (EXM) of CBRICK and PBRICK samples were measured by using an active radon gas analyzer with an accumulation container. The average value of EXS and EXM of CBRICK and PBRICK samples found as 45.9 ± 2.9 mBq m-2 h-1 and 3.7 ± 2.9 mBq kg-1 h-1 and 100.9 ± 4.7 mBq m-2 h-1 and 9.9 ± 0.5 mBq kg-1 h-1, respectively. Radiological parameters related to external and internal exposure to members of the public such as the radiation protection index, alpha index, and indoor absorbed gamma radiation dose rate and the corresponding annual effective dose from external exposure, annual effective dose from inhalation of radon, and the lifetime cancer risk were estimated for CBRICK and PBRICK samples. The results were compared with each other and with the international recommended limits or criteria. The results reveal that the average values measured and estimated for CBRICK samples are approximately two times lower than those measured and estimated for PBRICK samples. Thus, from the radiological viewpoint, clay brick is preferable to pumice brick as a structural material in the building sector. © 2018 Elsevier LtdThis study was carried out within the framework of a master thesis conducted at University of Nevşehir. The authors would like to thank Dr. Ahmet VARİNLİOĞLU and Turkish Atomic Energy Authority (TAEK)

Natural and fallout radioactivity levels and radiation hazard evaluation in soil samples

The present study aims to obtain the baseline data on natural and fallout radioactivity and to evaluate radiation hazards caused by ionizing radiation emitted from 226Ra, 232Th, 222Rn, 40K and 137Cs in surface soil samples collected from Mersin province and Akkuyu nuclear power plant region. The activity concentrations of 226Ra, 232Th, 40K and 137Cs were measured using a gamma spectrometer with HPGe detector. The activity concentrations of 226Ra, 232Th, 40K and 137Cs varied from 14.1 ± 0.7 to 65.4 ± 2.9, 12.0 ± 0.8–51.7 ± 2.1, 172.2 ± 15.8–511.1 ± 37.8 and <MDA to 86.2 ± 1.4 Bq kg-1, respectively. The average concentrations of radon in soil and air were estimated as 23.9 kBq m-3 and 76 Bq m-3. The radiological parameters such as absorbed gamma dose rate in outdoor air (DRout), annual effective dose rate from external exposure (EExt), annual effective dose rate from inhalation of radon (EInh) and lifetime cancer risk (LTCR) were calculated to evaluate radiological hazards. The average values of DRout, EExt, EInh and LTCR were found to be 51 nGy h-1, 62 µSv year-1, 715 µSv year-1 and 2.2 × 10-4, respectively. © 2016, Springer-Verlag Berlin Heidelberg

Determination of tritium activity concentration in natural water samples

This study aims to measure tritium activity concentrations in tap, well, and spring water samples from Mersin province in Turkey using a liquid scintillation counting (LSC) system and to evaluate the corresponding radiological hazards due to the ingestion of water samples. The tritium activity concentrations measured in the water samples varied from < 1.9 (detection limit) to 14.1 ± 1.0 Bq L-1 (119.5 ± 8.5 TU) with an average of 6.2 ± 0.6 Bq L-1 (52.5 ± 5.4 TU). The tritium activities in the water samples were significantly lower than the limit of 100 Bq L-1 for water intended for human consumption. The annual effective doses estimated for different age groups of the members of the public due to the intake of the tritium varied from 0.009 to 0.185 µSv y-1. © 2017 Taylor & Francis