Radioactivity Levels Research Articles

A low-cost instrumentation for monitoring of the environmental radioactivity

In this work, a low-cost radiation monitoring instrumentation for measuring the environmental gamma radioactivity together with some atmospheric parameters was designed and produced. The device has been built with market available components. The detector section of the device uses a Si-PIN photo-diode as an active element. A tiny current produced from the energy deposition of gamma rays in silicon is amplified in two stages, firstly with a charge sensitive amplifier (CSA) and secondly with a shaping amplifier (SA). The amplified signal is further processed to be converted into digital pulses for counting. The monitor station is designed to be operated remotely in self-sufficient mode, equipped with LoRA module running at 500 MHz to transfer the data remotely to a base station. The base station also includes a LoRA module to receive the data and stores it in an SD card while an OLED display visualizes the recent measurement. Multiple monitor stations can be used to control the radioactivity level in a field simultaneously. This field could be used inside or outside of an interested facility. The noise limit of the detector developed was determined to be as low as 20 keV photon energy. The low-energy detection limit was conservatively set to 40 keV which was still below the 64 keV of the naturally occurring 234Th. Counting the events for hourly, daily or weekly provide statistically significant data depending on the activity of the interested region. All gamma energies above 40 keV from the decays of naturally occurring radioisotopes can be practically observed with this device. The anomalies can be detected using various mathematical algorithms that can be embedded into the microprocessor and the results can be shared with the public.

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.

Determination of Radiological Hazards Associated with the use of Oba-Ile River Sediments as Building Material

This study was conducted to determine the radioactivity level in the sediment samples collected from Oba-Ile River, Olorunda Local Government Area of Osun State, Nigeria and evaluate the radiological hazards associated with the use of the river sediments as building material. Twenty four (24) sediment samples were obtained along three different points within the River for a period of eight months. The activity concentration of 40K in the sediment sample ranged from 273.36 ± 5.41 Bqkg-1 to 1662.41± 28.19 Bqkg-1with an average concentration 892.22 ± 14.66 Bqkg-1. The values of 232Th in the sediment samples ranged between 27.22 ± 5.12 Bqkg-1 to 186.14 ± 6.22 Bqkg-1 with an average concentration 87.95 ± 7.91 Bqkg-1. The values of 238U ranged from 12.61 ± 2.01 Bqkg-1 to 241.12 ± 5.91 Bqkg-1 with an average 62.83 ± 3.18 Bqkg-1. The radiological hazards due to natural radionuclides content, such as absorbed dose rate (DR), annual effective dose rate (AEDE),excess lifetime cancer risk (ELCR), internal radiation hazard (Hin) and external radiation hazard (Hex) in the sediment samples were calculated. The calculated radiological parameters were compared with recommended safety limits and internationally approved values.

Evaluation of radiological hazards associated with some Egyptian marble and granite rocks

The aim of the current study is to evaluate the radioactivity estimate the radiological risk of some granites and marbles rocks and explaining the cause of increased radioactivity in some types of rocks. The radioactivity of some granites and marbles produced in Egypt were determined by using a Germanium detector. Three types of marble (Breshia, Galala, and Trista) and three types of granite (Gandola, White Halayeb, and Red Aswani) were collected. All marble samples show low radioactivity with average activity concentrations of 20 ± 2, 4.50 ± 0.5, and 6.70 ± 1.2 Bqkg− 1 for 226Ra, 232Th, and 40K respectively. Granite samples have higher activity concentration with averages of 152 ± 7, 129 ± 8, and 1228 ± 15 Bqkg− 1 for 226Ra, 232Th, and 40K respectively which exceed the world average values of soil (32,45,412 Bqkg− 1 for 226Ra, 232Th, and 40K respectively) excluding Granite G.2 (white Halayeb) as it shows an insignificant level of radioactivity. The annual effective doses of marble samples Breshia, Galala, and Trista were measured to be 4.42 ± 0.4; 158 ± 14 and 153 ± 15 µSvy− 1, and 1008 ± 147, 80 ± 7 and 987 ± 45.0 µSvy− 1 for the granite samples Gandola, White Halayeb and Red Aswani respectively. The radiation hazard parameters show a higher value for granite samples than marble samples, primarily due to the presence of potassium feldspar minerals in these types of granites. marbles were observed to be radiologically safer than granite because they possess a neglected 40K content and a trace quantity of uranium and thorium. Moreover, the minimum potassium content is enough to make a rock radiological unsafe due to 40K only being determined to be about 13.2%.

Suppression mechanism contributing to the low leaching rate of cesium from incineration bottom ash

After the Fukushima Daiichi nuclear accident, municipal solid waste (MSW) contaminated with radiocesium was generated. In Japan, approximately 80% of MSW by weight has been incinerated. As consequence, radiocesium was retained in incineration residue after the accident. Among the incineration residues, fly ash with high radioactivity was transported to an interim storage facility and special treatment has been carried out. While, bottom ash with radioactivity levels of <8000 Bq kg−1 wet has been directly deposited in conventional MSW landfills. The radiocesium leaching from bottom ash is low, but the reason for this low leaching remains unclear. In this study, leaching tests and microscopic observations of bottom ash containing stable Cs were conducted to investigate the mechanism making Cs leaching low. It is noted that the ash used was simulated ash created from combusting refuse derived fuel (RDF) to which stable Cs was added, not real radioactive ash. Based on pH dependence testing, the Cs leaching increased as the pH decreased. The amount of Cs leached in the neutral range was 2–4% mass of the total content. Electron probe microanalysis, scanning electron microscopy, and energy-dispersive X-ray spectroscopy confirmed that certain particles in bottom ash contain concentrated Cs. These particles were found to comprise aluminum, silicon, potassium, and oxygen at their core, surrounded by concentrated Cs. Raman microscopy suggested that these particles are microcline. Co-heating of microcline with Cs carbonate led to the condensation of Cs in a manner similar to particles observed in bottom ash, and Cs was captured in a glassy substance formed on the microcline surface, which reduced the leaching of Cs.

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.

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.

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 &amp; 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 &amp;gt;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.

Risk Assessment and Natural Radionuclide Content in Black-Sand Deposits of North Sinai Coast, Egypt

The radioactivity levels and risk factors have been assessed for twenty-eight positions of Black-Sand (BS) surface deposits along the Mediterranean Sea coast of north Sinai, Egypt. Twenty-eight surface samples were collected from six local cities: El Ressa, Abo Sakl, Ghornata, El Arish, El Masaed, and El Rommana. The activity concentration values of the nuclides of the 226Ra, 232Th, and 40K of the collected samples were measured using a P-type HPGe detector with a relative efficiency of ∼ 100% where it is defined at 1.33MeV relative to a standard 3-inch diameter and 3-inch long NaI (TI) scintillator. El Ressa samples have relatively the most significant average values for 226Ra and 232Th, whereas El Rommana samples had the highest for 40K. The radiation hazard calculations for the collected BS samples indicated significantly lower values than the internationally recommended limits. The ambient dose rates of the six areas under study were monitored and found to range from 0.06 to 0.10 μSv.h-1.

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.

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.

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.