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The essential variables used to measure radiological pollution and related human health concerns include radionuclides’ distribution and transfer factors (TFs) in plants. The TF is the radionuclide’s specific activity (Bq kg −1 ) ratio in the plant to its dirt equivalent (in dry weight). This research aimed to determine the radionuclides’ soil-to-plant TF, to evaluate natural radionuclides’ transfer level from soil to a selected cultivated crop (wheat) in the Shaqlawa district of Erbil Province, Iraq. The study randomly collected soil and cultivated plant samples from various locations. The collected samples were analyzed using HPGe gamma spectroscopy. The 226 Ra, 232 Th, and 40 K radionuclides, the average TFs from soil to plant root were 0.032, 0.033, and 0.405, respectively. TF values indicate that approximately 3.2%, 3.3%, and 40.5% of 226 Ra, 232 Th, and 40 K, respectively, were transferred from the soil to the wheat, following the order of 40 K (0.40) > 232 Th (0.033) and 226 Ra (0.032). All TFs were below the global standard of unity. A positive Pearson correlation was found among the three radionuclides in soil and plant samples. The three radionuclides were detected in soil and wheat samples, and the positive correlation among them suggested they originated from a common source in each environmental matrix. The results confirmed that the TF values from soil to wheat are safe for agricultural lands in the Shaklawa district, with no immediate radiological health implications.

This study aims to assess the concentrations of natural radionuclides activity ( 226 Ra, 232 Th and 40 K) and calculate a number of radiation risk indicators in some types of field crops in different areas of Tikrit City - Salah Al-Din Governorate - Iraq. The measurement was carried out using a gamma ray spectroscopy connected with a scintillation detector crystallized with thallium-activated sodium iodide NaI(TI). The results were that t 0……he mean concentrations of elements ( 226 Ra, 232 Th and 40 K) wer (6.79±0.33 1B q/Kg ,10.79 ± 0.640 Bq/Kg , 133.34± 5.895 Bq/Kg ), respectively. And the radiation risk indicators were less than the international permissible and the recommended average, so that the samples under study are safe and suitable for human and animal consumption.

In this work, the concentrations of natural uranium, uranium isotopes, and the annual effective dose in the surface water for both of Al-Manathera and Al-Heerra regions of An-Najaf, Iraq were determined using a solid state, nuclear track detector, type (CR-39). The results show that the average of uranium concentrations in Al-Manathera and Al-Heerra regions were 1.75 ± 0.202 µg/l and 1.07 ± 0.152 µg/l respectively. The average of activities of 238U, 235U and 234U in Al-Manathera were in 6.48 ± 0.250, 0.100 ± 0.011 and 2.18 ± 0.252 Bq/l, while in Al-Heerra, they were 1.27 ± 0.188, 0.061 ± 0.008 and 1.33 ± 0.189 Bq/l, respectively. The total average of the annual effective dose of natural uranium in all water samples to the adult members of the population for both of Al-Manathera and Al-Heerra regions were 0.152 ± 0.017 µSv/y and 0.093 ± 0.012 µSv/y respectively. In addition, the outcomes demonstrate that uranium levels in the samples of water from Al-Manathera region were far toxic than the samples of Al-Heerra region, as they included uranium levels and total annual effective dose in all water samples of water that comply with the worldwide limits that are approved by International Commission on Radiological Protection (ICRP Publication, Ottawa, 21:1–3; ICRP, Recommendations of the International Commission on Radiological Protection, ICRP Publication, Ottawa, 1990 and Pergamum Press, Oxford; ICRP, Annals of the ICRP. ICRP publication 65, Pergamum Press, Oxford, 1993) which states that safe limits are (1.9 µg/L and 1 mSv/y) respectively. For that reason, one may conclude that the radioactive isotopes are not considered dangerous in case humans consumed it.

This study presents data on the gamma radiation shielding properties of differential compositions of molybdenum oxide (MoO₃) incorporated into borate-tellurite-magnesium glasses with a formula of B 2 O 3 –TeO 2 –GeO 2 –MgO. The borate-tellurite-magnesium glasses were made using the melt-quenching technique, where the total amount of MoO₃ ranged from 0 to 20 mol%. The experimental measurement was performed at three known gamma photon energies of 0.662, 1.173, and 1.322 MeV utilizing a gamma ray spectrometer NaI(Tl). The shielding parameters of borate-tellurite-magnesium glasses, including the linear attenuation coefficient (LAC), mass attenuation coefficient (MAC), half-value layer (HVL), mean free path (MFP), tenth-value layer (TVL) and the effective atomic number (Z eff ), are estimated. The results showed that the MoO 3 doping improved all the radiation shielding performance, especially at lower energies, due to the significant effective atomic number and density of the glasses. The sample S4 with 20 mol% MoO 3 had the largest LAC (0.3087 cm − 1 at 0.662 MeV) and minimum HVL (2.245 cm) for gamma attenuation. The MAC values of the MoO 3 -doped borate-tellurite-magnesium glasses were consistently better than those of other reported glass systems, providing improved radiation shielding performance over the measured energy range. The present study findings are indicative that the MoO 3 -doped borate-tellurite-magnesium glasses represent new materials for gamma radiation shielding.

The radon isotopes are not as significant as ( Rn) due to the decay of the natural radionuclides ( U), ( Th) and ( U) due to their short half-life, at most. ( Rn) can be classified as among the most harmful radioactive elements in the world. In this analysis, the closed-can technique was used with solid-state nuclear track detectors (CR-39). After forty days of closed dosimeter buried in the soil of the garden, and ninety days from the closed position in the air of some dwellings were collected dosimeter and stripped of nuclear detectors impact of closed groups. For 8 hours, CR-39 detectors were chemically etched by (6.25 N) NaOH solution at 70°C and then registered within an optical microscope. The levels of soil radon concentrations ranged from 28.44±0.58 to 479.76±2.43 Bq/m with a mean value of 220.33±1.64 Bq/m , while the concentration of radon in the air of certain dwellings varied from (1.95±0.27 to 46.82±0.75) Bq/m with an average value of 21.51±0.54 Bq/m . In comparison, the annual effective dose attributed to radon in soil ranged from 0.71±0.09 mSv/y to 12.10±0.38 mSv/y with an average value of 5.55±0.261 mSv/y, while the annual effective dose in air differed from (0.04±0.02 mSv/y) to (1.18±0.12 mSv/y) with an average value of (0.60±0.09 mSv/y). Neglecting the effects of other radon sources, the percentage share of the annual effective dose due to radon in soil measured in the air home, ranged from 0.005±0.001 to 0.453±0.074 with an average value of 0.130±0.040. Weak correlation between concentrations of radon in households and soil air. But roughly speaking, one can say that in soil air every 1000 Bq/m and 1000 mSv/y contributes around 130 Bq/m and 130 mSv/y in indoor air.

Using a high-purity germanium detector (HPGe), the natural and artificial radioactivity in soil samples taken from agricultural regions near the Al-Kasak oil refinery were examined. According to estimates, the average specific activities of 226 Ra, 232 Th, 40 K, and 137 Cs were 20, 15, 283, and 3.6 Bq kg −1 , respectively. The specific activities of 226 Ra, 232 Th, 40 K, and 137 Cs in the soil samples were comparatively lower than the average values of these radionuclides worldwide. The investigation also analyzed several radiological hazard indices. The hazard indices calculated in this study were utilized to assess the potential health risks associated with radiation in the soil. The results indicate that these indices are significantly below their permissible limits. Therefore, the soil in the study area does not pose any excessive radiation exposure to the inhabitants and can be safely used as construction material without presenting an immediate radiological threat to the public.

In the present work, the natural radioactivity of surrounding soil samples collected from Assuit cement factory (Egypt) have been measured by using NaI(Tl) detector. Gamma analysis for each sample along with the calculated specific activities shows that the average concentrations of Ra-226, Th-232 andK-40 were 31.44 ± 3.67 Bq kg-1, 39.77 ± 2.00 Bq kg-1 and 113.23 ± 5.66 Bq kg-1 respectively, where only the values of Ra-226 and K-40 are lower than the worldwide average, while the average value of radium equivalent activity, absorbed gamma dose rate, external and internal hazard indices, gamma index, alpha index, indoor and outer door effective doses for each sample were 132.02 Bq kg-1, 43.27 nGy h-1, 0.256, 0.346, 0.691, 0.157, 0.212 mSv y-1 and 0.0572 mSv y-1 respectively. All these values were found to be lower than the permissibility limit value.

This work aims to determine the transfer factors (TFs) of 40K, 226Ra and 232Th from soil to vegetables, because there are few surveys of them in Iraq. The samples were taken from three important agricultural areas supplying the vegetable products needed by the Iraqi population. Using NaI(Tl) technique, the average values of TFs of the above radioactive isotopes were found to be 0.60, 0.41, 0.59 and 0.05, 0.03, 0.05 from soil to dry and fresh samples, respectively. The radiation hazard indices and the total annual dose were found to be within the range of the world values.