Natural Radiation Dose Research Articles

Radon and Gamma Radiation Dose to the Population Residing Near the Uranium Mill Tailings Disposal Site in Uranium Mineralized Zone at Jaduguda

Members of the public residing in the villages situated near the uranium mill disposal site, such as those in the vicinity of uranium tailings ponds, may indeed be at risk of radiation exposure. Present study focuses to evaluate the radiological exposure condition for the resident of villages situated in nearby vicinity of the tailing disposal site in the uranium mineralized region of Jaduguda, Jharkhand, India. In this study, the dose from external gamma radiation and radon concentrations, both indoors and outdoors, is evaluated. The natural background radiation dose to the residents of villages located near the uranium mill tailings disposal site is estimated to be 2.99 mSvy-1. Radon and its decay products contribute approximately 57.6% of the radiation dose to the villagers, while gamma radiation accounts for 42.4%. Residents of villages near the uranium tailings ponds receive a radiation dose is within the typical range of global natural background radiation dose of 1-10 mSvy-1 to the members of the public.

Features, reasons, and significance of radon and thoron attributable radiological dose in the indoor environment

Humans receive around 50% of natural radiation dose due to 222Rn (radon), 220Rn (thoron) and their decay products. Several field campaigns measuring these gases and the decay products in different regions of India have been conducted in the recent past. Some of these studies measured indoor activity concentration and/or dose due to these gases and the associated decay products. This work compares the fraction of 222Rn and decay products and 220Rn and decay products in inhalation dose for 10 studies conducted in Uttarakhand state. It is seen that AEDT (annual effective dose due to 220Rn and decay products) for these regions varies between 21 and 48% and it is significantly higher than the averaged worldwide reference value of 6%. Based on elaborative measurements performed in the Bageshwar district (present work), Almora and Nainital districts (our previous campaigns); the reasons for this high value have been explored. It was observed that a higher source term for mud houses could be the main reason for the high AEDT range. Interestingly, preliminary analysis revealed that the fraction is higher for the dwellings situated at higher altitudes thus indicating the role of the unavailability of modern building construction materials at remote locations. The study highlights the significant contribution of thoron in the Indian Himalayas.

Natural Radioactivity and Consequent Radiation Dose on Environmental Media in Farmlands Around Ilokun Dumpsite Ado-Ekiti, Nigeria.

Natural Radioactivity and Consequent Radiation Dose on Environmental Media in Farmlands Around Ilokun Dumpsite Ado-Ekiti, Nigeria.

Hematological and neurological impact studies on the exposure to naturally occurring radioactive materials

Naturally Occurring Radioactive Materials (NORM) contribute to everyone's natural background radiation dose. The technologically advanced activities of the gas and oil sectors produce considerable amounts of radioactive materials as industrial by-products or waste products. The goal of the current study is to estimate the danger of long-term liability to Technologically Enhanced Naturally Occurring Radioactive Materials (TE-NORM) on blood indices, neurotransmitters, oxidative stress markers, and β-amyloid in the cerebral cortex of rats' brains. Twenty adult male albino rats were divided into two equal groups (n = 10): control and irradiated. Irradiated rats were exposed to a total dose of 0.016 Gy of TE-NORM as a whole-body chronic exposure over a period of two months. It should be ''The results showed no significant changes in RBC count, Hb concentration, hematocrit percentage (HCT%), and Mean Corpuscular Hemoglobin Concentration (MCHC). However, there was a significant increase in the Mean Corpuscular Volume of RBCs (MCV) and a significant decrease in cell distribution width (RDW%) compared to the control. Alteration in neurotransmitters is noticeable by a significant increase in glutamic acid and significant decreases in serotonin and dopamine. Increased lipid peroxidation, decreased glutathione content, superoxide dismutase, catalase, and glutathione peroxidase activities indicating oxidative stress were accompanied by increased β-amyloid in the cerebral cortex of rats' brains. The findings of the present study showed that chronic radiation liability has some harmful effects, that may predict the risks of future health problems in occupational radiation exposure in the oil industries. Therefore, the control of exposure and application of sample dosimetry is recommended for health and safety.

37 years after the chernobyl: the current radiation status in Kocaeli, Turkey

This study aims to assess the artificial and natural radiation dose levels in certain districts of Kocaeli province within the Marmara region, 37 years after the Chernobyl nuclear accident, and evaluate the current status prior to potential nuclear leakage events from Zaporijya or other nuclear power plants. Radioactive concentrations of 232Th, 238U, 40K and 137Cs were determined using HPGe gamma spectrometry in 26 soil samples collected from the region of interest. The average concentrations were found to be 22.35 Bqkg−1 for 238U, 26.36 Bqkg−1 for 232Th, 368.34 Bqkg−1 for 40K, and 2.44 Bqkg−1 for 137Cs. Furthermore, the study revealed an absorbed dose rate of 41.73 nGyh−1, an annual effective dose equivalent of 51.18 µSvy−1, and an excess lifetime cancer risk of 0.00018.

Measurement of natural ambient gamma radiation levels and estimation of population dose in tobacco-growing places of Karnataka state

Abstract Karnataka state is the fourth largest tobacco-growing state in India and Mysore district has large tobacco cultivation. The fertilizers contain the primary nutrients NPK (Nitrogen, Phosphorus and Potassium). This is also responsible for enhancing the gamma radiation level in rural areas of cultivated land of tobacco growing places, in addition to the natural gamma radiation. The aim and objectives of the present study consist of the measurement of the natural ambient gamma radiation dose level, and dose to the public. The natural ambient gamma radiation levels in some tobacco growing places of the Karnataka state were measured by a scintillation survey meter. The ambient gamma absorbed dose rate in cultivated and non-cultivated land varies from 34.8±0.3 nGyh-1 to 226.2±5 nGyh-1, with a mean value of 84.77±1.9 nGyh-1, and 26.1±0.3 nGyh-1 to 182.7±4 nGyh-1, with a mean value 58.82±1.2 nGyh-1 respectively. The indoor and outdoor gamma absorbed dose rate of the villages of the study area varies from 52.2±0.4 nGyh-1 to 234.9±4.5 nGyh-1, with a mean value of 100.89±2.3 nGyh-1, and 30.45±0.5 nGyh-1 to 165.3±3.5 nGyh-1, with a mean value of 63.19±1.3 nGyh-1 respectively. The annual effective equivalent dose rate of the study area varies from 0.293mSvy-1 to 1.344mSvy-1, with a mean value of 0.572mSvy-1. The indoor, tobacco leaves stored houses and the cultivated land shows higher gamma radiation dose rates than the outdoor atmosphere of the villages and non-cultivated land. The present study was able to establish a baseline data of Annual Effective Dose (AED) and assess gamma radiation dose rate of the study area. The results were presented and analyzed systematically from the radiation protection point of view.

Gamma radiation dose rate in high-altitude areas in the Bageshwar, Champawat and Pithoragarh districts of Uttarakhand, India.

Radiation has a deteriorating effect on humans as well as on the environment depending on its level, although we have all been exposed to natural gamma radiation from birth. The presence of radionuclides in rocks, soil, plants, and water is a major factor behind the natural gamma radiation. The present study deals with the study of natural gamma radiation at Bageshwar, Champawat and Pithoragarh districts of Uttarakhand. It also consists of seasonal variations in gamma radiation and its relationship with altitude and geology. The purpose of this study was to investigate the influence of altitude and geology on natural gamma radiation dose rate data in high-altitude areas of India. The highest gamma radiation value was 444nSv/h in the summer and 342nSv/h in the winter. The investigation recorded the gamma radiation up to 2542.20maltitude, indicating that the geology of the areas is more relevant than the altitude. Few sites in such a high-altitude zone were found to exceed the value of 200nSv/h, as reported by UNSCEAR. This research is necessary in order to consider the human health and climate changes, both of which are part of the action plan for the United Nation's Sustainable Development Goals (SDG 3, SDG 13).

Structural properties and electron spin resonance (ESR) dose estimations of fossil cow tooth enamel from Köşk Höyük, Turkey.

In this work, two cow teeth collected from the Niğde-Köşk Höyük excavation site in Turkey were studied for characterization and dosimetric purposes. Each tooth sample was prepared by applying mechanical and chemical methods to obtain the enamel fractions. To do this, mineralogical and elemental concentration properties of the tooth enamels were investigated by performing X-ray diffraction (XRD) and scanning electron microscopy coupled with energy-dispersive X-ray measurements (SEM-EDX). It was found that the enamel structures contained a highly hydroxyapatite crystalline without any characteristic impurities. The dose response of the tooth enamels was determined by using the electron spin resonance (ESR) method. Absorbed radiation doses were calculated as (26.05 ± 0.15) Gy and (25.48 ± 0.18) Gy by the additive dose method using both natural radiation doses and artificial irradiation doses of the enamel samples. It is concluded that these samples could be used to reconstruct radiation doses. This result can be considered as a precursor for future ESR dosimetry/dating studies of other fossil teeth at this excavation site.

Natural radioactivity for soil samples in primary schools at Najaf city, Iraq

Natural radiation is the most significant contribution to the annual exposure of the world population, making it essential to assess the quantity of natural radiation in soil. This research aims to assess the level of natural radioactivity within the soil samples taken from primary schools in Al-Najaf, Iraq using gamma-ray spectroscopy. Specific activity was determined for the 238U series (214Bi), 232Th series (218Tl), 40K, and 235U. Twelve radiological hazard indices were computed. SPSS software version 23.0 was employed for data statistical analyzes to include average, standard error, standard deviation, box plot, frequency distribution, and Pearson's correlation coefficient. The results of the concentrations of 238U, 232Th, and 40K, were drawn using a geographic information system (GIS) technique. The results showed that the average values and standard error of 238U, 232Th, 40K, and 235U were 20.1 ± 0.65 Bq/kg, 11.5 ± 0.22 Bq/kg, 330.9 ± 7.1 Bq/kg, and 0.926 ± 0.03 Bq/kg, respectively. The results of 238U, 232Th, 40K, and 235U were compared to the average world value. This indicates that some schools' 238U and 40K levels had exceeded the acceptable worldwide levels. At the same time, the results of radiological hazard indices were seen to be within the permissible worldwide levels. As a result, the elementary schools under study can be argued that they are relatively free of natural radiation threats. The resulted data of the current research might be contributed to the database of natural radioactivity levels and radiation doses received by those who come into touch with these schools.

Analysis of effective equivalent dose to the organs and cancer risk assessment due to natural outdoor gamma radiation in Eastern Thar Desert, India

ABSTRACT The assessment of a population’s radiological impact due to radiation emitted by natural radionuclides is important because it is associated with the health of the people. The objective of the study was to provide reliable baseline data and analyse the impact of the natural outdoor gamma radiation dose of Nagaur, Kheenvasar, and Jayal blocks of Nagaur district, Rajasthan. A total of 80 locations of Nagaur, 31 locations of Kheenvasar, and 51 locations of Jayal were selected for the analysis. The gamma radiation exposure was found to vary from 66 nSv/h to 163 nSv/h, which lies within the normal range specified by UNSCEAR (20 to 200 nSv/h) for all the sites. Statistical analysis through the Shapiro-Wilk test (p < 0.05) rejects the normality of data for all three blocks, which specified the not suitability of data for the parametric test. The Jonckheere-Terpstra test (p < 0.05) confirmed that there was no significant difference among the radiation doses of different blocks. Annual effective dose (AED) and Excess lifetime cancer risk (ELCR) were computed to determine the number of cancer cases originating from outdoor gamma radiation. Average cancer cases due to outdoor gamma radiation were estimated at 49, 45 and 48 per hundred thousand in Jayal, Kheenvasar, and Nagaur blocks, respectively. The Effective Equivalent Dose for Bone-marrow (red), colon, lung, stomach, breast, reminder tissues, Gonads, Bladder, Oesophagus, Liver, Thyroid, Bone surface, brain, salivary, glands, and skin was also calculated and found within the prescribed limit.

A review on natural gamma radiation dose levels and its health effects

Exposure to the natural background gamma radiations in both indoor and outdoor environments is inevitable. The long-term exposure to such radiations could result in lung cancer (sometimes leukaemia, CNS tumours); and hence it must be constantly monitored. In this paper, an attempt is made to review the background natural gamma radiation doses reported at various locations for the south Indian environment and it was found that the gamma levels in coastal regions were relatively higher than those in sub continental locations but in most of the locations the annual effective dose rate was within the permissible limits as per UNSCEAR

Evaluation and measurement methods for the surface radon exhalation rate of buildings

Half of the natural radiation dose to the human body comes from indoor radon and its progeny, inhaling of which plays a key role in the development of lung cancer. Given the relationship between the radon exhalation rate (RnER) and the indoor radon concentration, accurate determination and control of the former directly affect the control and protection of the latter. In this study, a method was developed to estimate the actual RnER of building walls through building material samples. The surface RnER of the wall of any thickness that was constructed of any building material could be calculated by its intrinsic RnER value and radon diffusion length, which could be obtained by measuring the RnER of the pre-treated building material sample models through the activated carbon box-γ spectroscopic method. The experimental results indicated that the deviation between the calculated wall surface RnER of the building and the measured wall surface RnER of the building was &lt;5.1%. Therefore, the intrinsic RnER of building materials could be regarded as an evaluation index for the RnER of buildings.

Radiological Hazard Related with Natural Radioactivity in Natural Gas Transportation—A Case Study from Poland

Activity concentration of 210Pb in black powder and gamma radiation dose rate related to natural gas transportation were discussed. As part of the research, the content of radiolead (210Pb) in black powder, spent filter containers, radon (222Rn) activity concentration in natural gas and gamma radiation dose were measured around selected points of natural gas transportation infrastructure in Poland. The content of some heavy metals was also analyzed. The average concentrations of 222Rn and 210Pb ranged from 30 to 1400 Bq/m3 and from around 450 to 16,000 Bq/kg, respectively. The external exposure to gamma radiation was low; the gamma radiation dose rate was at the level of background radiation or slightly exceeded it. The research demonstrated that the content of 210Pb in black powder is strongly related to radon concentration in natural gas, the volumetric flow rate of the transported natural gas and solid fraction content. Some black powder samples should be classified based on 210Pb content as low-radioactive waste.

Results of the 20-year period of functioning of the Federal Databank on the natural radiation doses to the population of the Russian Federation

This study is focused on the analysis of the results of the functioning of the Federal Databank on the doses to the public of the Russian Federation from natural and man-made modified radiation background as a part of Joint governmental system of control and accounting of the doses from ionizing exposure in 2001-2020. The mean individual annual effective dose of the public of the Russian Federation from natural sources of ionizing exposure, calculated based on the data from all measurements in 2001-2020, is equal to 3,36 mSv/year. The study includes the analysis of the problems and perspectives of the improvement of the system of the data collection on the levels of exposure of the public of the Russian Federation from natural sources.

General Overview of Radon Studies in Health Hazard Perspectives.

The adverse human health effects due to ionizing radiation are well known. Radon is the major source of background radiation among those that are of natural origin. It contributes about 55% of the natural radiation dose to humans. It is a colorless, odorless, and tasteless radioactive noble gas that comes from the natural radioactive decay series of uranium. Radon can be found everywhere in the atmosphere and become attached to aerosols in the air. The aerosols carrying radon and its progeny can be inhaled and deposited in different regions of the human respiratory tract. The deposited radioactive aerosols continue to decay and exposing the lung to ionizing radiation can destroy sensitive cells in the lung, causing a mutation that turns to be cancerous. Different countries and international and national organizations put their action levels to reduce radon lung cancer risk. The Environmental Protection Agency recommends 148 Bq/m3 as the action level. On the other hand, International Commission for Radiation Protection (ICRP) recommends 200 Bq/m3 as the action level. The main objective of this review is to focus on how radon is established as a health hazard, ways of radon detection and measurements, methods of reducing and controlling high indoor radon concentration, and what are the recommended international action levels of radon concentrations. It mainly focuses on the health perspective of radon studies because it is now a crucial and hot issue in the world. In most developing countries like our country Ethiopia, radon studies are not well investigated.

Ultra-safe nuclear thermal rockets using lunar-derived fuel

Rocket launch failure rate is slightly higher than five percent. Concerned citizens are likely to protest against private-sector launches involving fission reactors. Yet, fission reactors can power long-duration lunar operations for science, observation, and in situ resource utilization. Furthermore, fission reactors are needed for rapid transport around the solar system, especially considering natural radiation doses for crews visiting Mars or an asteroid. A novel approach is to create nuclear fuel on the Moon. In this way, a rocket launched from the earth with no radioactive material can be fueled in outer space, avoiding the risks of spreading uranium across Earth's biosphere. A solution is to harvest fertile thorium on the lunar surface, then transmute it into fissile uranium using the gamma ray fog which pervades the deep sky. It is only at lunar orbit, at the very edge of cislunar space, that the Earth-launched machine becomes a nuclear thermal rocket (NTR). Thorium is not abundant, but can be concentrated by mechanical methods because of its very high specific density relative to the bulk of lunar regolith. Thorium dioxide (ThO2) has an extremely high melting point, such that skull crucible heating can be used to separate it from supernatant magma. When filled into a graphite-lined beryllium container (brought from Earth) and set out on the lunar surface, high-energy gamma rays will liberate neutrons from the Be. After moderation by the graphite, these thermal neutrons are captured by the thorium nucleus, which is transmuted into protactinium (Pa91). This element can be extracted using the THOREX process, and will then decay naturally into U-233 within two or three lunar days. The uranium is oxidized and packed into fuel pellets, ready to be inserted into a non-radioactive machine, which now becomes an NTR. Additionally, hydrogen can be extracted from deposits in permanently-shadowed regions on the Moon, providing reaction mass for the NTR. A novel method of solid-state hydrogen storage, which can be entirely fabricated using in situ resources, can deliver said hydrogen to the fission reactor to provide high and efficient propulsive thrust. These combined operations lead to an ultra-safe (for the Earth) means for private sector, commercial transport and power generation throughout the Solar System. With the hydrogen storage material used as radiation shielding for crewed spacecraft, and greatly-reduced transit times relative to chemical rocketry, this innovative approach could fundamentally transform how humans work, play, and explore in outer space.

Natural background gamma radiation dose estimation in the surrounding villages of Devarakonda Town, Telangana State, India

Natural background gamma radiation dose estimation in the surrounding villages of Devarakonda Town, Telangana State, India

Estimation of unattached and aerosol-attached activities of airborne short-lived radon progeny in indoor environments

Inhalation of the airborne short-lived radon progeny is regarded as the most crucial way of internal exposure to the natural radiation dose delivered to the human lung. In this respect, this study aims to determine the unattached and aerosol-attached activities of radon progeny and to estimate some important physical parameters employed to assess the radiological impact of this radiation on humans. For this purpose, radioactive aerosol samples collected on polycarbonate membrane filters to measure total alpha activity by passive alpha dosimetric technique using CR-39 detectors in sixteen different locations including some houses and workplaces in El Jadida city, in Morocco. In addition, the room-specific parameters and aerosol physical processes that affect the unattached and attached activity concentrations were determined. The obtained experimental results by the three-count method and room model parameters were used as input data on a developed PC-based software that we have developed to solve mathematical equations and calculate required physical quantities. Accordingly, the individual activities of radon progeny namely 218Po, 214Pb, and 214Po as well as radon activity concentration were determined. Simultaneously, the unattached and aerosol-attached activity concentrations (Cju and Cja) of radon progeny were calculated based on the room model calculation. Consequently, some radiological quantities used in the calculation of the lung dose were estimated. The results showed that the indoor radon activity concentration in different targeted locations ranges between 38 and 143 Bq. m−3 with an average value of 84.8 ± 9.5 Bq. m−3. The average obtained values of the equilibrium-equivalent concentration (Ceq), unattached fraction (fp), and equilibrium factor (F) at low and good ventilation rates change respectively from (24 Bq. m−3, 0.08, and 0.25) to (34 Bq. m−3, 0.02, and 0.41). Under normal environmental conditions, the average obtained values of Ceq, fp, and F, in houses and at workplaces were (17 Bq. m−3, 0.07, and 0.25) and (32 Bq. m−3, 0.04, and 0.35) respectively. Depending on the different aerosol conditions and obtained values of unattached fraction fp, the calculated average values of dose conversion factors (DCFs) were 8.70 mSv.WLM−1 and 11 mSv.WLM−1 in houses and workplaces respectively. These values were in good agreement with the recommended values by ICRP, which are in the order of 9 mSv.WLM−1 and 12 mSv.WLM−1 for houses and workplaces respectively.

Calculation of natural external radiation dose rate for environmental impact assessment, case study: Abu Zenima area, Southwestern Sinai, Egypt

ABSTRACT The present article aims to assess environmental impact coming from terrestrial natural radionuclides, external gamma exposure dose radiation and the average effective annual dose value. The obtained data can be used to provide technical support for the social communication of nuclear energy bodies to understand the natural radiation background of the study area. To achieve the aim, 11271 measurements of 238U, 232Th and 40K were carried out using airborne gamma ray spectrometry for the study area. These measurements were used and converted in to specific activity for calculating the absorbed dose rate (D) and the annual effective dose (E) to infer the average annual effective dose value for the population of Abu Zenima area. The calculated specific activity of U238, Th232 and K40, absorbed dose rate, annual effective dose rate, collective dose and annual effective dose value for the population were mapped through Geographic Information System (GIS) using Arc map software version 10.5. The specific activity concentration of U238 ranged from 1 to 400 Bq/kg, Th232 ranged from 1 to 650 Bq/kg and K40 ranges from 1 to 4000 Bq/kg. The absorbed dose rate values ranged from 3.25nGy/h to 261 nGy/h. Annual effective dose rate values, varying from 21 to 9867 µSv y−1 with an average value of 172µSv y−1which is higher than the worldwide average value of 70µSv y−1 (for outdoor exposures from terrestrial radiation sources).The collective effective average dose (S), varied from 1.16 to 424.31 with an average value of 20.77 man mSv. Finally, average total population effective dose of Abu Zenima area ranged from 0.0013 to 0.0375 with an average value of 0.0129mSv. From all these results, it was concluded that Al Sahu, Al Nasb, Serabit El Khadim and Al Lehianlocalities have high background radiation.

Presence of Radionuclide Concentrations in Himalayan Region of Uttarakhand, IndiaA Review

Earth is a major source of several elements which are occurring with different physical and chemical properties in nature. Some of the elements are categorized as Naturally Occurring Radioactive Materials and termed as NORMs. These natural sources and anthropogenic sources combined make the earth’s environment radioactive and human beings continuously receive the amount of the total radiation dose more than 50% of the radiation that comes from radon and thoron. It has been evident that soil is the furthermost important feature that affects the radon/thoron level in the human living surroundings which increases human exposure to radioactivity. The concentration of natural radionuclides elements present in soil or rocks is the main feature of levels of natural background radiation dose. This review paper represents the activity level of Ra-226, Th-232, and K-40 in soil samples of the Himalayas region of Uttarakhand. The data so obtained from previous studies of radionuclides shows the high abundance of radioactive mineralization in the soil of the Himalayan region in the Uttarakhand state of India.