Potential Radiological Hazard Research Articles

Estimation of Background Radiation from A Soil Sample from A Barley Farm Area and Malt Factory in East Arsi, Ethiopia

The aim of this work is to estimate the background radiation of a soil sample from the barley farm area and Malt factory in East Arsi, Ethiopia. The technique of gamma-ray spectrometry with a high-purity germanium (HPGe) gamma-ray detector and a PC-based MCA was used. The activity concentration levels due to 40K, 137Cs, 238U, and 232Th were measured within the study area at a depth of 30 cm. The soils of the study region are used as construction material by many farmers. The measured specific activity of those radionuclides was compared with the data reported worldwide. The specific activity of radionuclides was estimated in both study locations. The specific activity 238U of soil samples ranged from 41.0 Bq kg-1 to 30.7 Bq kg-1 in the barley farm, with a mean value of 37.7 Bq kg-1, and for malt ranged from 23.8 Bq kg-1 to 40.6 Bq kg-1, with a mean value of 32.5 Bq kg-1. The specific activity of 232Th in soil samples ranged from 89.9 Bq kg-1 to 156.0 Bq kg-1, with a mean value of 118.6 Bq kg-1, whereas for the Malt factory ranged from 121.0 Bq kg-1 to 128.0 Bq kg-1, with a mean value of 123.7 Bq kg-1. In barley soil samples, the specific activity of 40K ranged from 401.0 Bq kg-1 to 530.0 Bq kg-1 with a mean value at the Malt plant ranged from 518 Bq kg-1 to 598.0 Bq kg-1, with a mean value of 553.6 Bq kg-1. Similarly, the specific activity of 137Cs was determined in both the barley farm and the malt Factory. In barley farm soil samples, it ranged from 3.3 ±0.6 Bq kg-1 to 5.34±0.6 Bq kg-1, and with a mean value of 4.3 Bq kg-1 whereas, in the Malt factory it varied from 3.1 ±0.7 Bq kg-1 to 5.3 ±0.7 Bq kg-1, and with a mean value of 4.5 Bq kg-1. The absorbed dose rate within the barley farm ranged from 24.6 ±2.9 nGyh-1 to 34.1 ±2.9 nGy h-1, and with a mean value of 30.6 nGyh-1, whereas, in the Malt factory, it varied from 31.3 ±1.3 nGy h-1 to 35.5 ±1.3 nGyh-1, and with a mean value of 33.5 nGy h-1. The annual effective radiation dose for BSS and MFSS was calculated to be 37.6 mSv y-1and 41.1mSv y-1. This study revealed that this region lies within a medium radiation background when compared with the world's average. The marginal value of dose is higher within the Malt factory area because of fertilizer consumption for cultivation. Since these estimated background and radiological impact factors are below the recommended values, it seems that there is no potential radiological health hazard related to the soils from both BSS and MFSS in Arsi Asella, Oromia, Ethiopia.

Evaluation of potential radiological hazards of unfired construction materials containing fly ash in Vietnam.

In this study, the specific activities of 226Ra, 232Th and 40K in the unfired construction materials (solid card bricks, 4-hole bricks, pavement bricks) containing fly ashand bottom ash from a coal-fired thermal power plant in Vietnam were measured using the low-level gamma-ray spectrometer with HPGe detector. Also, the 222Rn concentrations in these materials were analyzed using RAD7 radon monitor and then radon mass exhalation rate and emanation fraction of these materials were calculated. The potential radiological hazards for residents living in the model room made of these materials were evaluated. The average specific activity of 226Ra, 232Th and 40K were found as 67.7, 79.3 and 703.5Bqkg-1, respectively. The total annual effective dose (due to external gamma exposure and internal radon exposure for resident living in the CEN model room made of the unfired brick samples) was found as 0.9mSvy-1 which is lower than the worldwide average dose of 2.4mSvy-1. Calculations from ResRad-Build code showed that the doses due to radon exposure account for from 62.3% (at the first year) to 98.8% (at the next 30years) of the total gamma and radon dose. Under low air exchange to the outside environment, from the 6th year onwards, the total dose may exceed the average dose value from natural radiation exposure sources.

Activity concentrations and radiation hazard in the soil of Ashaka Cement PLC Gombe state, Nigeria with a multivariate statistical approach

Humans are exposed externally and internally in their environment to natural background radiation from radionuclides such as 40K, 238, U and 232Th which emit gamma, alpha, beta and other forms of radiation through their decay processes. These radionuclides are found in the soil, food and the water we consume. Human activities such as the mining of uranium, oil exploration, building materials, coal-fired power station can ignite the Naturally Occurring Radioactive Materials (NORMs). The aim was to assess radiation impact in Ashaka cement factory, Gombe state for their potential radiological hazards in order to maintain a safe environment. A prospective cross-sectional survey design was adopted and using a purposive sampling technique, fifteen (15) soil samples were collected using a geographical positioning system (GPS). The activity concentrations of these natural radionuclides were measured due to Gamma radiation by using a High Purity Germanium detector. Samples were analysed at the Radiation Protection Institute of Ghana Atomic Energy Commission, Kwanbeya District, at Accra, Ghana. Fifteen (15) soil samples were collected from within the Ashaka Cement factory (Zone 1) and environment (Zone 2). Data was analyzed by the use of SPSS Version 22.0 (IBM Corp. Armonk NY, 2011). Descriptive statistics was employed to obtain the Mean and Standard deviation of the radioactivity concentrations. Inferential statistics was carried out to compare the radionuclides and radiological parameters. Statistical significance was considered at p ≤ 0.05. The mean activity concentrations of 238U, 232Th and 40K in soil samples at Zone 1 are 42.70 Bqkg-1, 29.00 Bqkg-1, 375 Bqkg-1 and Zone 2 is 46.11 Bqkg-1, 35.00 Bqkg-1, 780.30 Bqkg-1respectively. Radiation hazard indices at Zone 1 and 2 shows the mean for External Hazard index, Internal Hazard index, Gamma Index, External Absorbed Dose Rate, Annual Effective Does Rate, External Annual Effective Does Rate, Excess Lifetime Cancer Risk and Annual Gonadal Effective Dose is 0.31, 0.42, 0.83, 38.80nGyh-1, 0.32x10-3, 0.048mSvyr-1, 0.17mSvyr-1, 371mSvyr-1 and 0.42, 0.55, 1.18, 45.70nGyhr-1, 0.46mSvyr-1, 0.056mSvyr-1, 0.20x10-3, 533.80mSvyr-1 respectively. This implies that both staffs and members of the public in the factory might be at risk due to cumulative effect of radiation exposure high activity concentration from 238U and Annual Gonal effective dose exceeding the world average limits.

Assessment of Radiation Levels and Potential Radiological Hazards in the Soils of Riruwai Mining Area, North-Western Nigeria

This research aimed to assess the levels of natural radionuclides in the soil of the Riruwai mining area and to evaluate the radiological hazards associated with them. A total of sixty soil samples were collected from four sampling sites during the dry and wet seasons. The concentrations of uranium-238 (238U), thorium-232 (232Th), and potassium-40 (40K) were measured using an HPGe gamma-ray spectrometer, and the measured concentrations were used to estimate the internal and external hazards and gamma dose rate. The results of the analysis indicated that the concentrations of 238U and 232Th in all sampling sites and seasons were higher than the world average. The radionuclide levels in the soils showed a significant seasonal variation, with higher concentrations obtained during the dry season. The correlation analysis revealed a very strong positive relationship between all the radionuclides, which indicates a common origin (parent material). The gamma dose rate computations revealed that only active and abandoned mining sites have a mean gamma dose rate greater than the tolerable limit of 59.00 nGy/h. The internal and external radiological hazards assessments showed that only the active mining sites had the potential to be hazardous to human health. The researchers, therefore, recommend that comprehensive monitoring of mining operations and public education about the dangers of radiation exposure in the study area be carried out.

Assessment of Natural Radioactivity Concentration and Radiological Risk in Tanjung Enim’s Coal Mine, South Sumatra Indonesia

Environmental radioactivity analysis has been carried out to determine the level of environmental radioactivity and the potential radiological hazards at Tanjung Enim’s coal mine. Gamma spectroscopy method has been carried out to identify radionuclides and their types of activity. The results of radionuclide concentration are used to determine the radiological hazard index and become input data for the Residual Radioactivity Onsite 7.2 application to determine the dose rate and long-term cancer potential received by workers in coal mines. The results obtained for the average concentration of radionuclide activity in coal samples are 226Ra, 232Th, and 40K are 72.468 Bq/kg, 86.905 Bq/kg, and 1802.049 Bq/kg, respectively. While the soil samples 226Ra, 232Th, and 40K respectively 79.205 Bq/kg, 100.209 Bq/kg, and 1443.275 Bq/kg. The radionuclide concentrations of both samples exceeded the UNSCEAR and worldwide reported averages for coal and soil. The average radiological hazard index for coal samples, namely Raeq, Hin, and Hex, was 335.500 Bq/kg, 1.102, 0.906, respectively. While the soil samples were 333.636 Bq/kg, 1.115, and 0.901, respectively. The index parameter is already lower than the UNSCEAR recommendation except for Hin, so there is a potential radiological hazard in internal pathways such as respiratory and digestive organs for mining workers. The total annual effective dose rate based on 5 RESRAD-Onsite 7.2 pathways, namely external gamma, inhalation, radon, soil ingestion, and drinking water, is 1.675 mSv/year, exceeding the dose limits determined by ICRP, 1 mSv/ year. The ELCR is 6.625×10-3 which exceeds the UNSCEAR recommendation, 2.4×10-4. Based on the results, it is necessary to intervene in the mining environment of the Tanjung Enim’s coal mine.

Statistical analysis of natural radioactivity measurements for the soil of Tiruvannamalai District, Tamilnadu, India

This study aims to analyse the radioactivity data of soil samples from Tiruvannamalai District of Tamilnadu, India using statistical methods. Statistical analysis is applied on 63 samples for measuring gamma emitting radionuclides (238U, 232Th &40K) and calculating radiation hazard indices. In this work conventional statistical analysis (Basic statistics and Frequency histogram) and multivariate statistical analysis (Pearson’s correlation coefficient analysis, Factor analysis and Cluster analysis) are employed. This analysis is also helpful to identify the existing relationships between the radiological hazard parameters and radionuclides, and consequently assessing the health exposure implications of the public to the studied soil. The results show that there is no potential radiological health hazard associated with the soil samples of the study area.

Evaluation of natural radioactivity levels and potential radiological hazards of common building materials utilized in Mediterranean region, Turkey.

Radiometric measurement of building materials is very important to assess the internal and external exposure caused by the ionizing radiation emitted from terrestrial radionuclides in building materials. The activity concentrations of 226Ra, 232Th, and 40K in fifty-eight samples of fifteen different structural and covering building materials commonly used in Osmaniye province located in the Mediterranean region of Turkey were measured by using gamma-ray spectroscopy. The activity concentrations of 226Ra, 232Th, and 40K varied from 2.5 ± 0.1 (marble) to 145.7 ± 4.4 (clay brick), 1.3 ± 0.1 (marble) to 154.3 ± 4.1 (marble), and 8.6 ± 0.2 (sand) to 1044.1 ± 70.3 (granite), respectively. Radiological parameters (activity concentration index, alpha index, indoor absorbed gamma dose rate and the corresponding annual effective dose rate, and excess lifetime cancer risk) were estimated to evaluate the health hazards associated with these building materials. Since the estimated values of these parameters are within the recommended safety limits or criteria values, the use of the studied building materials in the construction of dwellings can be considered to be safe for the residents of the region.

Green Tuff: Gamma Index in a Typical Building Material of Ciglio Area (Ischia Island)

Radiological characterization of tuff of Ciglio area in Ischia Island was performed to assess the potential radiological hazard associated with its use. For this purpose, high resolution gamma-ray spectroscopy was used. In five green tuff samples was measured the activity concentration of natural gamma-ray emitting radionuclides 226Ra, 232Th and 40K so, the mean gamma index was calculated. The mean value of the gamma index resulted lower than the reference level and it meets the dose criterion for the safety use of green tuff as building material.

Assessment of radiometric standard and potential health risks from building materials used in Bangladeshi dwellings

ABSTRACT Accurate knowledge of the terrestrial radionuclides concentrations in building components is crucial for radiation exposure assessment to the dwellers. The present investigation determines the natural radioactivity levels in common building materials (the structural and decorative) used in Bangladeshi dwellings via HPGe gamma-ray spectrometry. The measured activity levels of 226Ra, 232Th and 40K in the studied materials ranged between 7.33 ± 3.49 and 157.13 ± 13.03 Bq kg−1, 4.08 ± 1.84 and 131.65 ± 6.87 Bq kg−1 and 128.38 ± 10.27 and 1234.5 ± 39.77 Bq kg−1, respectively. Majority of the studied materials, especially the cement and paint, show the elevated concentrations of terrestrial radionuclides. However, for most of the samples, the total activity in terms of hazardous radium, show lower values compared to the OECD reported limiting index of 370 Bq kg−1, except in paint samples. The potential radiological hazards owing to the investigated samples were assessed by calculating a number established screening parameters, and compared with the agreed limits set by international regulatory bodies. The calculated indoor and outdoor absorbed dose rates for most of the materials (apart from sand) overdo the agreeing limiting standards of 84 and 59 nGy h−1, as suggested by UNSCEAR (2000). Therefore, continuous radiation level monitoring, especially for paint and cement samples, need to be continued to avoid undesirable exposure from radiation to occupants. Overall, the calculated data may help to set up recommendations for using building materials for dwelling resolutions.

Prediction of Potential Offsite TEDE, Excess Cancer Risk, Dominant Exposure Pathways, and Activity Concentration for Hypothetical Onsite Soil Contamination at the Proposed Rooppur Nuclear Power Plant

Abstract This study evaluates the potential offsite radiological hazards by calculating total effective dose equivalent (TEDE) and excess cancer risk if onsite soil contamination occurs at the proposed Rooppur Nuclear Power Plant (RNPP) site, Bangladesh. The assessment has been performed assuming a hypothetical soil contamination associated with Fukushima Nuclear disaster with the help of the RESRAD (residual radioactivity) OFFSITE computer program developed by Argonne National Laboratory, U.S. Six radionuclides, namely, Cs-134, Cs-136, Cs-137, La-140, Sr-90, and Te-129m have been considered. The maximum TEDE has been found approximately 2.8 mSv/yr whereas the maximum total excess cancer risk shows a value of 3.25×10−3. The number of dominant exposure pathways, maximum contributor pathways, and duration of dominance of different nuclides have been identified. Ingestion of fish is identified as the principal pathway to both TEDE and excess cancer risk. Time variation of activity concentration and dose/source ratio have also been studied.

Natural radionuclides distribution, depth profiles of caesium-137 and risk assessment for soil samples in west regions of China

An analysis of natural radioactivity in soils collected around Chinese Nuclear Test site is presented. The radioactivities of 238U, 226Ra, 232Th, 40K, and 137Cs were determined by HPGe gamma-ray spectrometry, and potential radiological hazards were evaluated. The depth profiles of radionuclides in three selected areas of Gansu were analyzed, and a new method for detection of 137Cs specific activities were measured using ultra-low background gamma spectrometer named GeTHU-II developed by Tsinghua University at China Jinping Underground Laboratory. The radioactivity concentrations of 137Cs were significantly different in these three areas and gradually decreased from surface to underground 15 cm.

Potential radiological hazard and options to cope with consequences from recycling of activated metal waste disposed of at a near-surface disposal facility

Based upon relevant statistics, it was suggested that potential scenarios for uncontrolled recycling of disposed activated metal waste, once it is excavated out of a near-surface repository, would not be excluded without prudent deliberation. Recycling a by-product slag from a smelter in parking lot foundation shows the highest radiation dose per unit activity concentration for 94Nb among combinations of twenty-one scenarios and seven radionuclides selected. The variability of calculation results were studied through deterministic sensitivity analyses, and probabilistic analyses were also conducted to understand the probability distribution of the resulting radiological risk. Case studies on activated large metal components dismantled from three nuclear power plants implied that the radiation dose may exceed the reference levels for inadvertent human intrusion. Accordingly, a few options to reduce the likelihood of excavation of activated metal waste in case of human intrusion and to limit its radiological consequence were proposed.

Estimation of Occupational Exposure during Ceramic Manufacturing

Introduction: The present study investigated the relatively high concentrations of natural radionuclides in raw material that used in ceramic manufacturing, and estimated the occupational exposure due to these activity concentrations. Material and Methods: A high-purity Germanium detector was used to determine naturally occurring radionuclides in raw materials that used in ceramic manufacturing. Activity concentrations of these materials lead to potential radiological hazards due to gamma and alpha radiation. These hazards were evaluated in the present study. Results: Maximum activity concentrations was5844, 1065 and 41 Bq/kg for 226Ra, 232Th and 235U in powdered quartz; however, maximum activity concentration for 40K was 1868 Bq/kg in colors. These activities were observed to be exceeding the exemption limit. Pancreasreceived the lowest dose (i.e., 0.02 mSv/y), while skin received the highest dose (i.e., 0.044mSv/y). Internal hazard index (Hin) was reported as 53.74, which exceed the recommended value (Hin≤1). Alpha index was 42.4 which led to over exposure. Representative level index and excess lifetime cancer risk were 0.00062 and 0.641 respectively. The total annual external dose was 2.62 m Gy/y which led to 1.83 mSv/y effective dose. Radiological hazard due to radon inhalation was 1.53E-06 mSv/y. Conclusion: Due to the high activity concentrations of raw materials (especially zirconium compounds) and consequently the associated high dose, specific regulations must be applied in the ceramic industry in Egypt.

Determination of factors affecting indoor doses from Malaysia’s ceramic tiles containing natural radionuclides

The level of natural radioactivity and radiological risks attributed to forty (40) different ceramic tiles using gamma-ray spectroscopy employing high-purity germanium detector were studied. The average activity concentrations of 226Ra, 232Th and 40K range from 37.5 ± 0.3 to 215.9 ± 5.8 Bq kg−1, 42.2 ± 0.1 to 181.8 ± 3.8 Bq kg−1 and 349.5 ± 25 to 1589.2 ± 21.1 Bq kg−1, respectively. The radium equivalent activity and activity concentration index were calculated to estimate the potential radiological hazards to the dweller. Furthermore, the factors affecting the total effective dose equivalent (TEDE) such as ventilation rate, room size and dweller position were investigated from the measured activity concentrations using RESRAD-BUILD computer code. The simulation results of TEDE from the variations of ventilation rate in a room range from 0.26±0.01 to 0.61±0.01 mSv y−1, on the other hand, the percentage variation of TEDE due to dweller position and room size are 35% and 33%, respectively. The calculated radiological risks parameters were all below the recommended maximum limit. Therefore, the radiological impact attributed from the ceramic tiles under study is negligible.

Radioactive investigation of Malaysia’s building materials containing NORM and potential radiological risks analysis using RESRAD-BUILD computer code

ABSTRACTThe activity concentrations of natural radionuclides from 80 samples of Malaysia’s building materials sourced from either manufacturers or local suppliers were studied using high-purity germanium (HPGe) detector. The radiological hazards associated with building materials under study were evaluated by calculating radium equivalent activity (Raeq). The calculated values of Raeq range from 29.7 ± 0.9 to 564.8 ± 13.6 Bq kg−1 with an overall average value of 198.1 ± 98.5 Bq kg−1. The calculated activity concentrations of 226Ra, 232Th and 40 K were further subjected to RESRAD-BUILD computer code with a view to determine long-term indoor external and internal doses received by a dweller from zero to 70 years. A significant variation in the indoor doses from zero to 30 years was observed while a relatively constant behaviour was observed from 30 to 70 years. The assessment of the indoor doses also showed that the indoor doses from walls are significantly high compared with indoor doses from the room floor. The calculated Raeq and long-term projection of indoor doses received by the dweller was below the recommended maximum values of 370 Bq kg−1 and 1000 µSv y−1, respectively. Therefore, the potential radiological hazards associated with building materials under study are negligible.

Assessment of TENORM and potential radiological hazards from the main brand glazed tiles produced in China with statistical analysis

ABSTRACT The activity concentrations of TENORM including 226Ra, 232Th and 40K of the ten main brands of glazed tiles produced in China and their radiological hazard parameters such radium equivalent radioactivity, alpha index, external exposure index, absorbed dose rate in air indoors, indoors annual effective dose, and activity concentration index are measured and estimated. The activity concentrations of 226Ra, 232Th, 40K in glazed tile samples are within the international tile reference values for 226Ra (30–200 Bq·kg−1), 232Th (20–200 Bq·kg−1) and 40K (160–1410 Bq·kg−1). The estimated mean values of radiological hazard parameters such as radium equivalent radioactivity, alpha index, external exposure index, indoors annual effective dose, and activity concentration index are also found to be below the international recommended limits or referenced values. The mean value of the absorbed dose rate in air indoors is within the country average range of 20–190 nGy·h−1. Moreover, combined with statistical analysis, it is concluded that the activity concentrations of 226Ra and 232Th in glazed tile samples have a strong correlation with the calculated radiological parameters, which has a significant impact on radioactivity in glazed tiles. Finally, it can be concluded that the ten brands of glazed tiles used in decoration of building materials are identified as grade A, which are unlikely to have a significant radiological hazard to the public. Therefore, the production, marketing and use scope of glazed tiles should be not restricted, but the early monitoring and classification should be done.

ASSESSMENT OF NATURAL RADIOACTIVITY LEVELS AND RADIOLOGICAL HAZARDS IN BUILDING MATERIALS

Radioactivity of 226Ra, 232Th, and 40K were measured in a total of 92 samples, including eight commonly used types of building materials that were obtained from local manufacturers and suppliers in Beijing. Concentrations were determined using high-purity germanium gamma-ray spectrometry. The 226Ra, 232Th, and 40K activity concentrations in all samples varied from 10.1 to 661, 3.3 to 555 and 3.2 to 2945Bq per kg with an average of 127.8, 114.8, and 701.5Bq per kg, respectively. The potential radiological hazards were estimated by calculating the absorbed dose rate (D), radium equivalent activity (Raeq), external hazard (Hex), and internal hazard (Hin) indices. The investigated building materials were classified into different types according to the radioactivity levels. Results from this research will provide a reference for the acquisition, sales, and use of building materials. Attention should be paid to the use of coal cinder brick, ceramic, and granite in the construction of dwellings.

First measurements of radon concentration in drinking water from taps, springs and wells in Oujda region, Morocco

Exposure to radon and radon progeny within the home and at work constitutes one of the greatest hazards from radiation. Radon is continually generated from uranium and thorium, which occur in many rocks and soil. The concentration of 222Rn was measured in tap, natural spring and well water samples gathered from several places from the north-eastern area of Morocco. This work aims to determine any potential radiological hazard for the local population which might be due to an inevitable high concentration of radon in drinking water. We utilised an AlphaGUARD radon gas detector to perform our measurements. The results show reasonable radon concentrations when compared with international recommendations.

Robotic Dispersal Technique for 35 GBq of 140La in an L-polygon Pattern.

In 2018, Defence Research and Development Canada, in partnership with Natural Resources Canada, led a field trial of survey and mapping of a large dispersion of radioactivity using Unmanned Aerial Vehicles (UAVs). The intent was to disperse La material in a 3,200 m L-polygon with an approximate activity level of 10 MBq m and to measure the radioactive material using sensors carried by UAVs. Due to the potential radiological hazard to personnel, the activity was approved only if Unmanned Ground Vehicles (UGVs) were able to completely handle and disperse the material remotely. One UGV was equipped with a traditional agricultural sprayer to disperse the material, and one UGV was equipped with a force feedback manipulator arm. Due to the freezing temperatures during dispersal, the 35 GBq of La was dispersed non-uniformly as one sprayer boom failed to perform as tested. However, rough analysis of the electronic dosimetry on the UGV concluded that 99% of the material was dispersed on the ground. The dosimeter placed closest to the robot manipulator arm, used for dispersal of material, indicated a contact dose of 33.5 mSv. The electronic dosimeter placed where the driver would have sat on the sprayer vehicle if it were not unmanned indicated a dose of 22.3 mSv. Thus, the use of UGVs for material dispersion substantially reduced the external exposure to personnel. The use of UGVs eliminated the potential of internal exposure as well. The Radiation Safety Officer received the highest dose at approximately 3 μSv, with the majority of the exposure coming from the handling of the Type A container.

Assessment of natural radioactivity levels and associated radiological hazard in scale and sludge from Jubilee oilfield of Ghana

Knowledge of accurate radio-isotopic signatures and chemical constituents is essential in assessing potential radiological hazards to the public and workers from exposure to NORM waste. For that reason, scale and sludge samples from Ghanaian oilfields were assessed using alpha spectrometry, gamma spectrometry, radon monitoring and scanning electron microscope techniques. Activity concentration of 238U, 232Th-series and 40K radionuclides for NORM residues have been evaluated. Fourteen trace elements were also identified and semi-qualitatively quantified. The obtained results clearly reflect that scale and sludge may present radiological risk for workers, public and environment.