Radioactivity Levels Research Articles

Radioactivity Levels and Heavy Metal Concentration in Mining Areas in Zacatecas, Mexico

The state of Zacatecas (Mexico) is one of the places most affected by pollution from the mining industry. A total of 21 samples from two areas were collected (6 samples from zone A and 15 samples from zone B) to evaluate the level of radioactivity and the degree of contamination with heavy metals. The activity concentration for 238U and 232Th was within typical values but that of 226Ra exceeded the value of 60 Bq kg−1 in both areas. In some places, the concentration of 40K was higher than the world average according to UNSCEAR. The radium equivalent activity Raeq and outdoor gamma exposure dose (D) indicated that some sites presented a radiological risk for the population. The excess lifetime cancer risk (ELCR) presented a higher risk than the world average in both sampled areas. Other parameters, such as the radiation index Ri, the external risk index Hex, and the internal risk index Hin, also indicated that there was a greater risk due to radiation exposure in these areas. In the case of heavy metals, some parameters, such as the EF, the Igeo, and the CF, showed that some places in zone A and zone B were contaminated with As and Pb. However, the concentration of selenium obtained by ICP-MS in the sampled soil was higher than the average in the Earth’s crust, both in mine waste dumps and in unaltered soil, which indicated that the background concentration for selenium in these places is higher than the world average.

RBIO-05. IPAX-2: PHASE 1 SAFETY AND DOSE FINDING STUDY OF [131I]IPA PLUS STANDARD OF CARE IN PATIENTS WITH NEWLY DIAGNOSED GLIOBLASTOMA

Abstract BACKGROUND Glioblastoma (GBM) overexpresses the L-type amino transporter (LAT) 1 & 2, which supports internalization of the therapeutic small-molecule amino acid derivative, 4-L-[131I] iodo-phenylalanine ([131I]IPA) and its companion diagnostic, 18F-FET. Previous studies of [123I]IPA SPECT have shown uptake by >85% of gliomas. Results from a phase 1 trial (IPAX-1) that explored [131I]IPA + radiotherapy in patients with recurrent GBM demonstrated a favorable safety and tolerability profile and promising efficacy. The objective of IPAX-2 (NCT05450744) is to evaluate the safety and tolerability of [131I]IPA in patients newly diagnosed with GBM. METHODS IPAX-2 is a phase 1, multicenter, open-label, single-arm, parallel-group, dose-finding study to evaluate the safety of ascending radioactive dose levels of [131I]IPA + best standard of care in newly diagnosed patients with GBM. Eligible participants (N=12) will be 18-65 years of age with histologically-confirmed intracranial GBM following surgical resection; no prior systemic therapy or radiation for GBM; a Karnofsky Performance Status ≥70; a plan to begin chemoradiation 3-6 weeks after surgical resection with Stupp regimen; adequate organ function; and adequate tissue samples previously archived. Four cohorts will encompass a 3 + 3 dose escalation, with [131I]IPA administered in 2 fractions corresponding to ½ of full dose activity via intravenous infusion (2x3.0 GBq, 2x4 GBq, 2x5 GBq, 2x6 GBq). Dose 1 will be administered prior to external beam radiation therapy (EBRT), and Dose 2 will be administered following completion of EBRT. 18F-FET PET will be used to identify suitable candidates with LAT1/2 overexpression, establish a baseline, and provide quantitative follow-up information. Primary outcome measures are 1) incidence rate treatment-emergent adverse events and 2) safety and tolerability by determining the dose-limiting toxicity, maximum tolerated dose, and recommended phase 2 dose. DISCLOSURES: Telix Pharmaceuticals is the sponsor of this study.

Numerical modelling for the distribution of 137Cs and 131I in the scheldt basin after a potential nuclear accident

Using the discontinuous Galerkin method in the SLIM modelling framework, we study the transport in the Scheldt basin and adjacent coastal area of radionuclides possibly emitted by Doel nuclear power plant in the aftermath of an accident. The contamination pathways taken into consideration are direct liquid releases into the water and deposition via the atmosphere. In past nuclear accidents, several radionuclides were released, among which, 131I and 137Cs were considered herein. The hydrodynamics and atmospheric conditions are selected to simulate the worst-case scenario in the domain of interest. The radionuclide deposition towards the North Sea results in 131I and 137Cs being transported to the Belgian coastal region. In case of deposition towards the river, radioactivity from upstream tributaries can reach the estuary within days. Direct liquid releases spread downstream until the mouth of the estuary after about few weeks and extend upstream into the Scheldt River. In all cases, due to tidal influence, the estuary becomes most vulnerable, with radioactivity potentially circulating for over a month. Additionally, higher river discharge resulted in decreased radioactivity levels in the estuary.

Evaluation of natural radioactivity levels and radiation hazards of Nkalagu limestone deposit, southeastern Nigeria.

Levels of natural radioactivity due to 40K, 232Th, and 226Ra in limestone deposits and corresponding surface soil samples from the Nkalagu community of Ebonyi State were investigated. Gamma spectroscopic analysis using a NaI (TI) detector was employed to measure the activity concentrations (ACs) of the natural radionuclides in the collected samples. The average AC of 226Ra, 232Th, and 40K was found to be 64.62 ± 11.63, 54.27 ± 8.52, and 313.06 ± 25.33Bq/kg, respectively, in limestone, whereas in the soil, the value was 60.80 ± 11.71, 44.97 ± 10.74, and 185.90 ± 18.20Bq/kg, respectively. Except for 40K, the obtained mean ACs of the radionuclides were in excess of the worldwide averages reported by the United Nations Scientific Committee on the Effect of Atomic Radiation (UNSCEAR). The mean value of Raeq, Hex, Hin, Iγ, and AUI was obtained as 166.33Bq/kg, 0.45, 0.62, 1.18, and 1.28, respectively, in the limestone, and 139.42Bq/kg, 0.38, 0.54, 0.98, and 1.12, respectively, in the surface soil. The radiation doses in limestone ranged from 120.78-168.89 nGyh-1 and 63.86-88.88 nGyh-1 for indoor and outdoor, respectively, whereas in the soil, the range was 104.47-129.77 nGyh-1 and 54.60-68.02 nGyh-1 for indoor and outdoor, respectively. The total annual effective dose ranged from 0.671 to 0.937 mSvy-1 with an average of 0.800 mSvy-1 in limestone and 0.579 to 0.720 mSvy-1 with an average of 0.667 mSvy-1 in the soil. Values of representative gamma index and activity utilization index, and indoor and outdoor radiation doses in limestone were above the recommended world average of ≤ 1, and 84 nGyh-1 and 59 nGyh-1, respectively, suggesting a restriction in the use of the limestone in construction of houses. The study therefore recommends that the use of limestone in building construction, especially in house interiors, should be discontinued.

Assessing radioactivity levels in agricultural soil: a comparative study of traditional vs. modern fertilization techniques in Tunisian oases.

To establish a radiological national reference for agricultural soil across Tunisian oases and assess the risk to human health associated with date consumption, with a focus on comparing the impact of traditional and modern fertilization, radiological parameters and activity levels of 22⁶Ra, 232Th, and 4⁰K were determined for 27 oases. These oases were located in three southern Tunisian governorates. The activity concentration of 22⁶Ra, 232Th, and 4⁰K was measured using a 3 × 3 inch NaI(Tl) scintillation detector, which was found to be 21.82 ± 1.0 , 26.51 ± 1.1 , and 559.21 ± 23.0 , respectively, for traditional oases and 26.56 ± 1.2 , 24.45 ± 1.1 , and 661.28 ± 26.3 , respectively, for modern oases. In addition, ambient dose equivalent rate was measured during sampling using a multipurpose hand-held radiation CsI(Tl) detector, which was found to be 0.075 µSv/h in traditional oases and 0.078 µSv/h in modern oases. The resulting radiological parameters and activity concentrations were then compared to results from neighboring countries and the average soil activity worldwide.

Limited uptake of [14C]Gardenia Blue administered orally in male and female rats and mice.

Gardenia blue (GB), a widely used plant-derived food color is prepared by reaction of genipin, the aglycone of geniposide, with protein hydrolysate. Recent animal studies investigating GB toxicity have indicated blue coloration in the gastrointestinal tract, kidneys and mesenteric lymph nodes in rodents following dietary administration. This study investigated the uptake and disposition of [14C]GB in male and female rats and mice administered 100 or 1000 mg/kg by gavage. [14C]GB was prepared by reaction of [2-14C]genipin with soy protein hydrolysate. Following administration in rats, 14C was eliminated primarily in feces (89-97% of administered dose), exhaled volatile organic chemical (VOC) and CO2 traps contained no radioactivity, and urine contained 0.2-0.4 %. In bile-duct-cannulated rats (100 mg/kg [14C]GB), 0.25% of dose was recovered in bile, and in urine, 0.5%. The percent of the dose absorbed was 0.9%, based on radioactivity in urine, bile, and carcass minus digestive tract contents. The highest level of radioactivity in tissues was in kidney; however renal recovery was low, with only 0.02-0.04% of the dose recovered in kidney. Repeated dosing indicated that 14C accumulated in kidney, and was slowly removed following cessation of dosing, consistent with previous studies, in the absence of any functional or histopathological changes.

Assessment of natural radioactivity levels in polymetallic nodules and potential health risks from deep-sea mining

The activity concentration of U-238, Ra-226, Pb-214, Bi-214, and Pb-210 was measured in samples of polymetallic nodules stored in the repository of the Interoceanmetal Joint Organization (IOM) based in Szczecin, Poland. The nodule samples were collected from the seabed of the Pacific Ocean, within the Clarion-Clipperton Zone, approximately 2,000 kilometres west of Mexico. The activity concentration of U-238 in the studied samples ranged from 9 to 51Bqkg-1. The mean activity concentration of the other radionuclides, Ra-226, Pb-214, Bi-214, and Pb-210, was found to be at comparable levels at 350, 321, 323, and 287Bqkg-1, respectively. Also investigated was the potential radiological hazard to individuals involved in the storing and processing of the nodules, resulting from the radioactive decay of Ra-226 contained in the nodules. It was concluded that the effective dose limit (20mSv) for individuals occupationally exposed to radioactive material can be exceeded in the case of prolonged and close contact with large quantities of nodules. Effective protective measures against the detected radiation include: observing the exposure time, ensuring safe distance from the source of radiation, and selecting suitable shielding where feasible within the operational constraints of the nodule transport or storage system.

Radiological hazard assessment of the soil in Daquq district, Kirkuk, Iraq

Abstract This investigation assessed the baseline levels of radioactivity in the soil of Daquq district, Iraq, using the GR-460 radiation detection system. 238U, 232Th, and 40K’s specific activities were measured and the hazard indices’ values determined. The average values of the absorbed dose, annual effective dose equivalent, annual gonadal equivalent dose, and lifetime cancer risk radiological risk factors were estimated. It is important to note that some of these results exceeded the global average levels. Various multivariate statistical techniques were employed to explore the relationships between the radioactive variables and identify potential correlations amongst them. Cluster analysis was utilized to identify clusters or groups of variables that shared similar characteristics. The study aimed to gain insights into the relationships between the radioactive variables and identify any correlations between them. These analyses provided valuable information regarding the associations and patterns within the data, thus contributing to an improved understanding of the radioactive variables and their potential implications.

Assessment of radioactivity levels and dose metrics in coastal drinking water sources of Odisha and Andhra Pradesh, India

Assessment of radioactivity levels and dose metrics in coastal drinking water sources of Odisha and Andhra Pradesh, India

Assessment of natural radioactivity levels in rice samples and their implications for radiological protection

ABSTRACT This study investigates the levels of natural and artificial radioactivity in rice samples collected from various local markets in Islamabad, Pakistan. The 226Ra, 232Th, and 40K activity concentrations were measured through gamma-ray spectrometry with a NaI(Tl) detector. The average activity concentrations were 1.67 ± 1.19 Bq kg−1 for 226Ra, 3.31 ± 1.83 Bq kg−1 for 232Th, and 88.51 ± 11.65 Bq kg−1 for 40K. Calculated radium equivalent (Raeq) values ranged from 7.35 to 18.08 Bq kg−1, with a mean value of 11.11 Bq kg−1, all below the permissible maximum of 370 Bq kg−1. The absorbed dose rates ranged from 6.85 to 16.39 nGy h−1, with an average of 10.64 nGy h−1, falling below the acceptable limit of 51 nGy h−1. The outdoor and indoor radiation hazard indices (Hex and Hin) had mean values of 0.03, both below the threshold value of one. The external and internal hazard indices (Iγ and Iα ) were both 0.088, also below the critical value of one. The excess lifetime cancer risk (ELCR) ranged from 0.28 to 0.11, with a mean value of 0.18, which is less than the critical value of one. Overall, the radioactivity levels in the analyzed rice samples are within the acceptable limits set by the International Commission on Radiological Protection and are below global averages. These results offer important insights into the radiological safety of rice consumption in the study area.

Evaluation of radioactivity levels and hazard indices of Th-232, Ra-226 and K-40 in sediment and water samples of Lake Victoria, Jinja, Uganda

This study evaluates the levels of natural radioactivity in sediment and water samples from Lake Victoria in Jinja, Uganda, with a focus on the radionuclides potassium-40 (40 K), radium-226 (226Ra), and thorium-232 (232Th). We investigated four distinct zones around the lake: fishing (Zone A), farming (Zone B), domestic/livestock (Zone C), and a control zone (Zone D). A total of 15 sediment samples and 15 water samples were collected and analyzed. Sediment samples were obtained using a gravity corer, with a maximum penetration depth of 50 cm. 40 K ranged from 170.479 to 524.883 Bqkg−1 across all zones, 226Ra ranges from 1.51 to 56.78 Bqkg−1 across all zones, and 232Th ranges from 18.18 to 73.10 Bqkg−1 across all zones. 40 K concentrations were highest in the farming zone, likely due to the use of nitrogen, phosphorus, and potassium (NPK) fertilizers. 226Ra and 232Th levels were also elevated in the farming zone, suggesting potential contributions from phosphate fertilizers. Absorbed dose rates varied across the zones, ranging from 28.33 to 58.17 nGyh-1. The measured absorbed dose rates across all zones were within the global average of 59 nGyh−1. The effective annual dose rate ranged from 0.35 to 0.91 mSvy−1 across all zones. Effective annual dose rates did not exceed the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) recommended limit of 1 mSv y−1, indicating low risks to public health from sediment radioactivity. The external index was below the safety threshold, suggesting minimal health risks. In water samples, gross alpha and beta activity concentrations were analyzed. Zone B had the highest average alpha activity concentration (0.64 BqL−1) and beta activity concentration (0.72 BqL−1), while Zone A had the lowest for both alpha (0.16 BqL−1) and beta (0.25 BqL−1) activity concentrations. Gross beta activity was generally higher than gross alpha activity, reflecting potential anthropogenic influences. Most water samples were within the UNSCEAR recommended limits for drinking water quality, except in areas affected by agricultural runoff. This study demonstrates that while the sediments of Lake Victoria in Jinja, Uganda, exhibit varying levels of naturally occurring radionuclides influenced by farming practices, the overall radiation exposure remains within safe limits. Continuous monitoring and regulatory measures are essential to maintain these safety levels and mitigate potential risks from increasing agricultural activities.

Self-Enhanced Electrochemiluminesence of Dye-Doped Polymer Dots for Coreactant-Free Visualized Detection of Iodide Ions.

The monitoring of radioactive iodide levels is of great significance in environmental science and cancer radiotherapy. In this work, a high-throughput, radiation-resistant, and visualized electrochemiluminescence (ECL) strategy was developed for detection of iodide ions. Herein, the hydrophobic ruthenium derivative (Ru(bpy)3[B(C6F5)4]2) (bpy = bipyridyl) was doped in tertiary amine-coupled polymer dots (N-PFO Pdots) to synthesize self-enhanced Pdots (Ru@Pdots), which showed extremely high ECL intensity in absence of coreactant. Due to the efficient ECL resonance energy transfer between Ru(bpy)3[B(C6F5)4]2 and N-PFO, the Ru@Pdots exhibited 18 times higher ECL intensity compared with bare N-PFO Pdots. Besides, Ru@Pdots also showed 220-times higher ECL intensity compared with Ru(bpy)3[B(C6F5)4]2 doped coreactant-dependent Pdots (Ru@PFO Pdots). Using Ru@Pdots as ECL emitters, an ECL imaging array was designed for iodide ion detection, which exhibited a detection range of 0.8 nM-4 μM and a limit of detection of 0.1 nM. In this strategy, iodide ions were oxidized as iodide free radicals on the surface of the electrode, which could further consume the nitrogen radical of Ru@Pdots and effectively quench the ECL signal. This method also showed good specificity, radiation-resistant performance, and accuracy in actual seawater sample testing, which indicated its value in marine environmental monitoring, nuclear security, and cancer radiotherapy.

Assessment of radiological risk to workers and members of the public from the operation of a groundwater treatment plant in Jordan

ABSTRACT The study aimed to evaluate the radiation doses received by workers at a pilot water treatment plant (WTP) in Jordan. It also examined the concentrations of gross alpha, gross beta, and radium activities in both groundwater and treated water, along with a radiological risk assessment for the waste generated by the treatment process. The radioactivity levels of gross alpha and gross beta in the groundwater were found to exceed the established drinking water limits. In the pilot WTP, two methods were applied for water treatment, namely, ceramic ultra-filtration (CUF) and reverse osmosis (RO), both of which produced treated water that met drinking water quality standards. The annual effective dose from external radiation exposure to the WTP workers was found to be less than 0.007 mSv y−1 (during the filters backwash operation). However, the average annual dose from internal radiation due to inhalation of radon released from groundwater reached 3.2 mSv y−1, exceeding the 1 mSv y−1 limit. Therefore, monitoring radon levels in workplaces is recommended. Radioisotope concentrations in the waste (sludge) stockpiles exceeded clearance levels, requiring them to be treated as radioactive waste. Overall, the WTP successfully produced drinking water that met quality standards, and the methods used could be replicated in other locations.

ASSESSMENT OF THE LEVELS OF NATURAL RADIOACTIVITY AND THE POSSIBILITY OF RADIATION RISKS IN SOIL SAMPLES TAKEN FROM DIFFERENT LOCATIONS IN SOUTHERN ALMAZAR-ALKARAK, JORDAN

A wide study of environmental radioactivity levels in soil samples from Southern Almazar-Alkarak in Jordan was performed to develop a radiological map of the area. 15 soil samples were collected from different locations across the region and subjected to analysis using a high-purity germanium detector (HPGe). The study showed that the average levels of natural radionuclides 226Ra, 232Th, 238U and 40K were 34.5±0.98, 25.6±1.3, 32.2±3.7 and 278.5±15.7 Bq.kg−1, respectively. Also, to evaluate the radiological danger, the radium equivalent activity (Raeq) is calculated, absorbed gamma dose rate (D), annual effective dose equivalent (AEDE) and external hazard index (Hex), internal hazard index (Hin). The average values for these parameters were determined to be 92.5 Bq.kg−1, 43.0 nGy h−1, 52.7 µSv y−1 and 0.25Bq.kg−1, 0.34Bq.kg−1 respectively. The values of the gathered samples stay below the allowable limits. Consequently, the examined region does not present any radiation risk to the general population. Moreover, it has been discovered that there is no concentration of 137Cs radionuclide activity in the studied area.

Radioactivity levels and radiological risk assessment in west Antalya beach sands

Radioactivity levels and radiological risk assessment in west Antalya beach sands

Determination of natural radioactivity levels in soil samples from irrigated vegetable farming land in and around Addis Ababa, Ethiopia.

Soil samples were collected from vegetable agricultural areas in and around Addis Ababa, and their levels of radioactivity were measured. Gamma spectrometry with high-purity germanium detector was used to quantify radioactivity level. The average concentration of 226Ra, 232Th, and 40K were 32.8±2.1, 62.4±4.4, and 544.3±23.3Bqkg-1 respectively. The mean values of 232Th and 40K are higher, whereas the value of 226Ra is comparable with world average values. Radiological hazard indices, including radium equivalent activity (Raeq), absorbed dose rate (Dr), outdoor annual effective dose equivalent (Deff), external hazard index (Hex), internal hazard index (Hin), and gamma radiation representative level index (Iγ), were calculated based on the activity concentration of 226Ra, 232Th and 40K. The mean values were 163.9Bqkg-1, 78.7 nGy h-1, 0.10mSv y-1, 0.44, 0.53, and 0.60 respectively. All indices are lower than global recommended limit values. These results revealed that radiation hazard due to radionuclides in the soil of the study area is insignificant.

Evaluation of Radioactivity Concentration and Hazard Indices in ash Some Hospitals Incinerators in Baghdad / Al Resafa

Due to their harmful effects on human health and their tendency to cause cancer, radionuclide concentrations and risk indicators have been measured in hospital incinerator ash. This was done by collecting samples ash of Hospitals Incinerators, examining them, and identifying the risks that emerged from the examination. Three samples Only taken for the study from certain hospitals affiliated with the Baghdad Al-Rusafa Health Department. High purity germanium gamma spectrometer (HPGe) were used to analyze the samples. The concentrations of potassium isotopes (K-40) range from (147.1±16.5 to 214.4±21.1 Bq/kg), While the range of concentrations for Ra-226 isotopes is (7.52±1 to 19±1.8 Bq/kg), and lead (Pb-212) isotope concentrations ranged from (10.1±1.1 to 11.1±1.5 Bq/kg). In addition, the isotope concentration of actinium (Ac-228) is 8.05±1. Radium equivalent (), risk index , annual effective dose equivalent radioactivity level index ), absorbed dose rate D, and lifetime cancer risk were calculated. The results showed that no radiation risk Only indicated by any of the risk indicators. This indicates that the ash from the hospital incinerator does not pose any radioactive danger.

A study on in-situ characterization technology development for clearance verification of radioactive waste from nuclear decommissioning

Although the clearance level of every radioactive nuclide was published by the IAEA to promote the recycling and reuse of decontaminated radioactive waste worldwide, technical and regulatory issues have always been raised around the application of the criteria. Therefore, several countries are developing in-situ characterization equipment or apparatus for on-site verification to check if the clearance criteria is met.In this study authors developed a pilot radiation detection and measurement system using in-situ characterization technology to solve the issues, which consists of a 3D scanning camera system and a built-in Monte Carlo simulation program. Measurement results show that MDA (Minimum Detectable Activity) of the current design was indisputably below the clearance level and built-in Monte Carlo simulation package closely predicts the measurements results with the error of less than 5%. This implicates that it can determine with enough margin whether the radioactivity level of decontaminated metallic components meets the clearance criteria at decommissioning site or not.Practically when we measure the radioactivity from gamma ray source mass attenuation always takes place during the photon transports through the medium. In fact, the reduction depends on the material, shapes, and radioactive sources. In this study the reduction factors were experimentally examined according to the influencing parameters and the results were saved as DCF (Density Correction Factor) in the data base. As expected, it turned out that the factor is somewhat affected by medium material and radioactive sources, but it is basically proportional to the distance of gamma ray passage.It is expected that upgraded design with more accurate and reliable instruments can make it easier for regulators to accept the application of the in-situ characterization technology on-site.

Radiation doses assessment and radon exhalation rate from the soils of Albyda area, Yemen

This work focuses on evaluating the potential health hazards posed by natural radionuclides in soil samples collected from 20 different sites in the Albyda area, Yemen. The activity concentrations of 226Ra, 232Th and 40K and radon exhalation rates in the soil samples were investigated. Alpha GUARD detector was used to estimate 222Rn concentration, while activity levels for natural radionuclides were measured by HPGe detector. The average values obtained for 226Ra, 232Th, and 40K were 27.60 ± 2.40 Bq/kg, 35.07 ± 2.45 Bq/kg, and 544.71 ± 48 Bq/kg, respectively, and for 222Rn concentrations were 135 ± 15 Bq/m3. Our findings show that the concentrations of radionuclides were within the limits of the world average established by UNSCEAR, except the concentrations of 40K, which was slightly higher than the world average (420 Bq/kg), while the average 222Rn concentration was lower than the ICRP reference level of 300 Bq/m3, and the average area exhalation rate 3.46 × 10−5 Bq m−2 s−1 was lower than the UNSCEAR world average of 0.016 Bq m−2 s−1. Therefore, the soil in this study does not pose any radiological hazard to the population due to the harmful effects of ionizing radiation. The results of the current study highlight the potential health hazard posed by radon and radioactivity levels in the soil samples from Albyda area, Yemen, which will help to increase awareness of the radiological hazard and the data could also be used as a reference for future research on radioactivity mapping in the study area.

Measurement of natural radiation levels in some soil samples from the ancient city of Borsippa in Babylon Governorate, Iraq

Abstract In the present study, the activity concentration of natural radionuclides was determined for 40K, 232Th, and 238U. Some samples of soil from the ancient city of Borsippa in Babylon Governorate. The detector sodium iodide activated by Thallium NaI (Tl) has been used to perform the radioactivity measurements. 15 samples had their natural radioactivity levels assessed. 40K, 232Th, and 238U had average specific activities of (167.86±1.19, 25.15±1.09, and 11.75±0.457) Bq/kg. The average radium equivalent (61.17±2.10) Bq/kg. Average internal and external risk factors were (0.15±0.00007, and 0.19±0.00027), As for the average value of the index of representative levels (Iᵧ) was (0.44±0.018) The average absorbed dose level in (nGy/h) (28.19±1.18). The results of this study were within the internationally permissible limits, according to the report of the United Nations Scientific Committee on the Effects of Atomic Radiation.