A Comparative Study of the Radiological Hazard in Sediments Samples from Drinking Water Purification Plants Supplied From Different Sources

The natural radiation level has been determined for 135 sediment samples from forty-six drinking water purification plants supplied from different sources (Nile River, Ibrahimia Canal and Bahr Yousif Canal) with an aim of evaluating the radiation hazard. The concentration of natural radionuclides (226Ra, 232Th and 40K) has been investigated byusing gamma spectrometry (NaI (Tl) 3″x 3″) detector. The results showed that the concentrations of average activity in the sediment samples collected from drinking water purification plants supplied from Nile River, Ibrahimia Canal and Bahr Yousif Canal are (29±2, 30±2 and 240±8 Bq kg-1), (47±3, 46±8 and 258±12 Bq kg-1) and (28±2, 27±3 and 219±18 Bq kg-1) for 226Ra, 232Th and 40K, respectively. In general, the distributions of average activity concentrations of samples underinvestigation are within the world values although some extreme values have been determined. Radiological hazard effects such as: absorbed dose rate (D), outdoor and indoor annual effective dose equivalent (AEDE), radium equivalent activities (Raeq), hazard indices (Hex and Hin), gamma index (Iγ), excess lifetime cancer risk (ELCR) and annual gonadal doseequivalent (AGDE) for the corresponding samples were also estimated.Key words: Drinking water purification plants, Sediment, Radiological hazard indice

A Comparative Study of the Radiological Hazard in Sediments Samples from Drinking Water Purification Plants Supplied From Different Sources

The natural radiation level has been determined for 135 sediment samples from forty-six drinking water purification plants supplied from different sources (Nile River, Ibrahimia Canal and Bahr Yousif Canal) with an aim of evaluating the radiation hazard. The concentration of natural radionuclides (226Ra, 232Th and 40K) has been investigated by using gamma spectrometry (NaI (Tl) 3″x 3″) detector. The results showed that the concentrations of average activity in the sediment samples collected from drinking water purification plants supplied from Nile River, Ibrahimia Canal and Bahr Yousif Canal are (29±2, 30±2 and 240±8 Bq kg-1), (47±3, 46±8 and 258±12 Bq kg-1) and (28±2, 27±3 and 219±18 Bq kg-1) for 226Ra, 232Th and 40K, respectively. In general, the distributions of average activity concentrations of samples under investigation are within the world values although some extreme values have been determined. Radiological hazard effects such as: absorbed dose rate (D), outdoor and indoor annual effective dose equivalent (AEDE), radium equivalent activities (Raeq), hazard indices (Hex and Hin), gamma index (Iγ), excess lifetime cancer risk (ELCR) and annual gonadal dose equivalent (AGDE) for the corresponding samples were also estimated

Natural radioactivity levels and radiological hazards indices of chemical fertilizers commonly used in Upper Egypt

In order to determine the radiological hazards indices of chemical fertilizers commonly used in Upper Egypt, The concentrations of natural radionuclides 226Ra, 232Th and 40K in seven types of chemical fertilizers used in Upper Egypt have been measured by gamma spectrometry using NaI (Tl) 3″ × 3″ detector. The ranges of concentration levels of 226Ra, 232Th and 40K were 12 ± 0.6–244 ± 12.6, 3 ± 0.2–99 ± 4.9, and 109 ± 5.5–670 ± 34 Bq kg−1, respectively. In the other side, the range values obtained from fertilizer samples under investigation were (33.1–392.3 Bq kg−1), (0.6–2.7), (15.6–177.8 nGy h−1) and (20.1–229.1 μSv y−1) for radium equivalent activity, γ-radiation hazard index Iγr, Dose rate (nGy h−1) and annual effective dose equivalent (AED) in the air to the occupational workers, respectively. The obtained values were compared with available reported data from other countries in literature. Keywords: Radioactivity, Chemical fertilizers, Radiological hazard

Mechanical, physical and gamma ray shielding properties of xPbO-(50-x) MoO3-50V(2)O(5) (25 <= 45 <= mol %) glass system

In this study, five different glasses encoded Pb25, Pb30, Pb35, Pb40 and Pb45 based on xPbO- (50-x) MoO3-50V(2)O(5) (25 <= x <= 45 mol %) glass system were fabricated. MCNPX code, XCOM and XMuDat have been utilized to compute the mass attenuation coefficient (mu(m)) values of the xPbO-(50-x)MoO3-50V(2)O(5) glass system at 0.015-15 MeV photon energies. X-ray diffraction (XRD), was characterized for fabricated glasses. Moreover, different shielding parameters such as Half Value Layer, Tenth Value Layer, relaxation length, effective atomic numbers and effective electron densities, basic gamma-ray attenuation properties such as Exposure Buildup Factors (EBF) and Energy Absorption Buildup Factors (EABF) at different penetration depths, Effective Removal Cross Section against fast neutrons have been calculated. In addition to nuclear radiation shielding parameters, numerous physical and mechanical parameters were determined. The experimental elastic modulus results were compared using the theoretical models Makishima-Mackenzie and Rocherulle model. The values of these moduli have been compared to their experimental values. The results observed that the composition has the highest value of PbO (45 mol. %) showed excellent nuclear radiation shielding and elastic properties

(59.5-x) P2O5-30Na(2)O-10Al(2)O(3)-0.5CoO-xNd(2)O(3)glassy system: an experimental investigation on structural and gamma-ray shielding properties

In this study, five different glasses encoded ND1, ND2, ND3, ND4 and ND5 based on (59.5-x) P2O5-30Na(2)O-10Al(2)O(3)-0.5CoO-xNd(2)O(3)(x = 1, 2, 3, 4 and 5 mol%) glass system were fabricated. Using two gamma- ray energies emitted from point sources, 356 keV (Ba-133) and 662 keV (Cs-137), gamma-ray attenuation coefficients were measured as a function of the Nd(2)O(3)concentration. The theoretical values of the mass attenuation coefficient were calculated using the XCOM program at 0.015-15-MeV photon energies. As it is underlined in the results section, the mass attenuation coefficient increases as the Nd(2)O(3)concentration increases. X-ray diffraction (XRD) was characterized for fabricated glasses. Moreover, different shielding parameters such as half-value layer (HVL), mean free path (MFP), effective atomic numbers (Z(eff)), basic gamma-ray attenuation properties such as exposure buildup factors (EBF) and energy absorption buildup factors (EABF) at different penetration depths were calculated. With increasing Nd(2)O(3)additive in glass samples, half-value layer (HVL), average free path (MFP), exposure and energy absorption buildup factor (EBF and EABF) values decrease. On the other hand,Z(eff)values increase with increasing Nd(2)O(3)additive in glass samples at the photon energy 0.015-15 MeV. The results highlighted that ND5 sample with highest value of Nd2O3(5 mol%) showed excellent nuclear radiation shielding properties