Average Absorbed Dose Rate Research Articles

Distribution and environmental impacts of heavy metals and radioactivity in sediment and seawater samples of the Marmara Sea

In this study, the natural and anthropogenic radioactivity levels in the sediment samples collected from the Marmara Sea in Turkey were determined. The average activity concentrations (range) of 226Ra, 238U, 232Th, 40K and 137Cs were found to be 23.8 (13.8–34.2) Bq kg−1, 18.8 (6.4–25.9) Bq kg−1, 23.02 (6.3–31.1) Bq kg−1, 558.6 (378.8–693.6) Bq kg−1 and 9.14 (4.8–16.3) Bq kg−1, respectively. Our results showed that the average activity concentrations of 226Ra, 238U and 232Th in the sediment samples were within the acceptable limits; whereas the average activity concentration of 40K in the sediment samples was higher than the worldwide average concentration. The average radium equivalent activity, the average absorbed dose rate and the average external hazard index were calculated as 100.01 Bq kg−1, 48.32 nGy h−1 and 0.27, respectively. The average gross alpha and beta activity in the seawater samples were found to be 0.042 Bq L−1 and 13.402 Bq L−1, respectively. The gross alpha and beta activity concentrations increased with water depth in the same stations. The average heavy metal concentrations (range) in the sediment samples were 114.6 (21.6–201.7) μg g−1 for Cr, 568.2 (190.8–1625.1) μg g−1 for Mn, 39.3 (4.9–83.4) μg g−1 for Cu, 85.5 (11.0–171.8) μg g−1 for Zn, 32.9 (9.1–73.1) μg g−1 for Pb and 49.1 (6.8–103.0) μg g−1 for Ni. S5 station was heavily polluted by Cr, Cu, Ni and Pb. The results showed that heavy metal enrichment in sediments of the Marmara Sea was widespread.

NATURAL RADIOACTIVITY IN SEDIMENTS AND RIVER BANK SOIL OF KALLADA RIVER OF KERALA, SOUTH INDIA AND ASSOCIATED RADIOLOGICAL RISK.

The paper presents the activity concentrations of 232Th, 226Ra and 40K in the sediments and river bank soil samples collected from the Kallada river environs of coastal Kerala. The radiological risks associated with these radionuclides were calculated. The samples were processed following standard procedure, and activity was counted using a high-efficiency 5″ × 5″ NaI (Tl) detector coupled to GSPEC gamma spectroscopy system. The mean values of measured activities of 232Th, 226Ra and 40K in soil samples were found to be 98.1 ± 0.4, 60.3 ± 1.1 and 343.4 ± 1.8 Bq kg-1, respectively, which results in an average absorbed dose rate of 103 nGy h-1 The corresponding values for sediment samples were found to be 88.0 ± 0.4, 48.6 ± 0.9 and 423.2 ± 2.0 Bq kg-1, respectively, with a resulting absorbed dose rate of 95 nGy h-1 Radium equivalent activity, annual effective dose equivalent, the external and internal hazard indices were determined and compared with recommended limits. The results of the work provide background data on natural radioactive isotopes, which are useful in the assessment of human radiation exposure from natural environment. The accumulation of information on natural radiation is of great value for radiation protection.

The Status of Natural Radioactivity and Heavy Metals Pollution on Marine Sediments Red Sea Coast, At Safaga, Egypt

Natural 226Ra, 232Th and 40K radio nuclides concentration in beach Sediments along Safaga coast of Red sea, Egypt has been carried out using a NaI (Tl) gamma ray spectrometric technique. The total average concentrations of radionuclides ± uncertainty of 226Ra, 232Th and 40K were 22.2 ± 1.7, 19.2 ± 2.5, and 477.6 ± 27.6 Bqkg-1, respectively. The total average absorbed dose rate is found to be 41.4 nGyh-1, whereas the annual effective dose rate has an average value of 54 μSvy-1. The total organic matter (TOC), carbonates (CaCo3) and Heavy metals distribution have been measured at some locations, the concentration for the investigated heavy metals overtake the allowable limits recommended by the Canadian Environmental Quality Guidelines, this assigned to the ratio of metals pollution is caused by anthropogenic activities (phosphate shipment as in Abu Tartour harbor and navigation as in Touristic harbor) and or by natural impacts such in mangrove interment. Statistical analyses were carried out between the parameters obtained from the radioactivity to know the existing relations and to study the spatial distribution of radionuclide.

Natural radioactivity levels in soils, rocks and water at a mining concession of Perseus gold mine and surrounding towns in Central Region of Ghana.

Levels of naturally occurring radioactive materials prior to processing of gold ore within and around the new eastern concession area of Perseus Mining (Ghana) Limited were carried out to ascertain the baseline radioactivity levels. The study was based on situ measurements of external gamma dose rate at 1 m above ground level as well as laboratory analysis by direct gamma spectrometry to quantify the radionuclides of interest namely; 238U, 232Th and 40K in soil, rock, ore samples and gross alpha/beta analysis in water samples. The average absorbed dose rate in air at 1 m above sampling point using a radiation survey metre was determined to be 0.08 ± 0.02 μGyh−1 with a corresponding average annual effective dose calculated to be 0.093 ± 0.028 mSv. The average activity concentrations of 238U, 232Th, and 40K in the soil, rock, and ore samples were 65.1 ± 2.2, 71.8 ± 2.2 and 1168.3 Bqkg−1 respectively resulting in an average annual effective dose of 0.91 ± 0.32 mSv. The average Radium equivalent activity value was 257.8 ± 62.4 Bqkg−1 in the range of 136.6–340.2 Bqkg−1. The average values of external and internal indices were 0.7 ± 0.2 and 0.9 ± 0.2 respectively. The average gross alpha and gross beta activity concentrations in the water samples were determined to be 0.0032 ± 0.0024 and 0.0338 ± 0.0083 Bql−1 respectively. The total annual effective dose from the pathways considered for this study (gamma ray from the soil, rock and ore samples as well as doses determined from the gross alpha/beta activity concentration in water samples) was calculated to be 0.918 mSv. The results obtained in this study shows that the radiation levels are within the natural background radiation levels found in literature and compare well with similar studies for other countries and the total annual effective dose is below the ICRP recommended level of 1 mSv for public exposure control.

Current Status of Absorbed Dose Rate in Air in Metropolitan Tokyo due to Radionuclide Deposition in Asphalt Pavements after the Fukushima Nuclear Power Plant Accident

Introduction The distribution of environmental radiation in eastern Japan was dramatically changed after the Fukushima Daiichi Nuclear Power Plant (F1-NPP) accident that occurred in March 2011. The released total amounts of artificial radionuclides were estimated to be 100 - PBq of 131I and 6 - 20 PBq of 137Cs and they are about 10% and 20% of the respectively estimated amounts emitted in the CHERNOBYL accident. In metropolitan Tokyo, 220 km southwest of the F1-NPP, such artificial radionuclides as 131I, 134Cs and 137Cs were wet-deposited on March 21 - 23 by rainfalls. According to the Tokyo Metropolitan Government , the average absorbed dose rate in air (range) that was observed in June 2011 was 61 ± 24 nGy h-1 (30 - 200 nGy h-1), and that value was a maximum of 4.1 times higher than measured values before the accident . The area with the highest dose rate due to radionuclides deposited from the F1-NPP accident was Katsushika Ward which is located in the northeastern part of Tokyo. The absorbed dose rate in air measured in July 2011 in Katsushika Ward was 268 nGy h-1, which was 6.9 times higher than the value before the accident (i.e., 39 nGy h-1). Higher absorbed dose rates in air were observed on both the western end and the eastern end including Katsushika Ward, of Tokyo. However, the contribution ratio from the radio cesium (134Cs + 137Cs) to the absorbed dose rate in air in the eastern end was twice as high as that of the western end.

Assessment of natural radioactivity levels and identification of minerals in Brahmaputra (Jamuna) river sand and sediment, Bangladesh

Distribution of the natural radionuclides (238 U,232 Th, and 40 K) and their specific activities in sands and sediments of the Brahmaputra (Jamuna) river of Bangladesh together with mineral characteristics has been studied to assess the radiation levels as well as to develop a baseline database for comparison in the future in case of any change in the area under study due to anthropogenic activities. The radiological parameters of natural radioactivity were assessed calculating the radium equivalent activity, hazard index, the absorbed dose rate, and annual effective dose. The average activity concentrations of 226 Ra (238 U),232 Th, and 40 K in sand and sediment were found to be 59 ± 2 & 60 ± 2 Bq/kg, 113 ± 5 & 135 ± 5 Bq/kg, and 983 ± 42 & 1002 ± 43 Bq/kg, respectively. The calculated average absorbed dose rate and annual effective dose were found to be 150 nGy/h and 0.18 mSv/year respectively. These high values are associated with mineral content of the sediment. X-ray diffraction peaks of sand and sediment samples identify quartz, feldspar, rutile, zircon, monazite, uranium fluoride, hematite, kyanite, and uranium arsenide minerals to be present in the samples.

A century of oil and gas exploration in Albania: Assessment of Naturally Occurring Radioactive Materials (NORMs)

The Naturally Occurring Radioactive Materials (NORMs) that are potentially generated from oil and gas extractions in Albania have been disposed of without regulations for many decades, and therefore, an extensive survey in one of the most productive regions (Vlora-Elbasan) was performed. A total of 52 gamma ray spectrometry measurements of soil, oil-sand, sludge, produced water and crude oil samples were performed. We discovered that relatively low activity concentrations of 226Ra, 228Ra, 228Th and 40K, with concentrations of 23±2Bq/kg, 23±2Bq/kg, 24±3Bq/kg and 549±12Bq/kg, respectively, came from the oil-sands produced by the hydrocarbon extraction of the molasses formations. The mineralogical characterizations and the 228Ra/40K and 226Ra/40K ratios of these Neogene deposits confirmed the predictions of the geological and geodynamic models of a dismantling of the Mesozoic source rocks. The average activity concentrations (±standard deviations) of the radium isotopes (226Ra and 228Ra) and of the 228Th and 40K radionuclides in soil samples were 20±5Bq/kg, 25±10Bq/kg, 25±9Bq/kg and 326±83Bq/kg, respectively. Based on the measurements in this study, the future radiological assessments of other fields in the region should be strategically planned to focus on the oil-sands from the molasses sediments. Disequilibrium in the 228Ra decay segment was not observed in the soil, sludge or oil-sand samples within the standard uncertainties. After a detailed radiological characterization of the four primary oil fields, we concluded that the outdoor absorbed dose rate never exceeded the worldwide population weighted average absorbed dose rate in outdoor air from terrestrial gamma radiation.

Absorbed dose rate in air in metropolitan Tokyo before the Fukushima Daiichi Nuclear Power Plant accident.

The monitoring of absorbed dose rate in air has been carried out continually at various locations in metropolitan Tokyo after the accident of the Fukushima Daiichi Nuclear Power Plant. While the data obtained before the accident are needed to more accurately assess the effects of radionuclide contamination from the accident, detailed data for metropolitan Tokyo obtained before the accident have not been reported. A car-borne survey of the absorbed dose rate in air in metropolitan Tokyo was carried out during August to September 2003. The average absorbed dose rate in air in metropolitan Tokyo was 49±6 nGy h(-1). The absorbed dose rate in air in western Tokyo was higher compared with that in central Tokyo. Here, if the absorbed dose rate indoors in Tokyo is equivalent to that outdoors, the annual effective dose would be calculated as 0.32 mSv y(-1).

Measurement of natural radioactivity in granites and its quartz-bearing gold at El-Fawakhir area (Central Eastern Desert), Egypt

The distribution of natural radionuclides (226Ra, 232Th and 40K) in Granites and its quartz-bearing gold at El-Fawakhir area (Central Eastern Desert, Egypt) were measured by using γ-ray spectroscopy [NaI (Tl) 3″ × 3″]. X-Ray Fluorescence technique was used for chemical analyses of the studied samples. The specific activity of 226Ra, 232Th and 40K values are in range (3 ± 0.5 to 43 ± 2 Bqkg−1), (5 ± 0.7 to 41 ± 2 Bqkg−1) and (128 ± 6 to 682 ± 35 Bqkg−1) respectively. The absorbed dose rates ranged from 13.8 to 58.4 nGy h−1, where the total effective dose rates were determined to be between 16.7 and 70.9 μSvy−1. The maximum external hazard index (Hex) is 0.3 nGyh−1. The calculated values of the excess lifetime cancer risks (ELCR) and annual effective dose rate values are in between (8.48 × 10−5 and 2.63 × 10−4) and (24.2 and 72.9 μSvy−1) respectively. Geochemically, the studied granites consist of major oxides, they are characterized by SiO2, K2O, Na2O, Al2O3, and depleted in CaO, MgO, TiO2, and P2O5. The average absorbed dose rate (Do) in air is 37.8 nGyh−1 for the whole studied samples, this value is about 3.78% of the 1.0 mSvy−1 recommended by (ICRP-60,1991) to the public, so there is no radiological risk for the workers in that area.

Natural Radioactivity in Soil Samples in Nineveh Province and the Associated Radiation Hazards

The natural radioactivity due to presence of 226 Ra, 232 Th and 40 K in soil of Nineveh zone, Nineveh province, Iraq were measured by using gamma-ray spectrometry based on high-purity germanium detector. The specific activity of soil samples ranged from 16.21 to 38.83 Bq/kg with an average of value of 32.52±6.48 Bq/kg, 8.53 to 28.37 Bq/kg with an average of 20.30±5.36 Bq/kg, 236.03 to 613.11 Bq/kg with an average of 378.93± 123.29Bq/kg, and 2.18 to 17.92 Bq/kg with an average of 8.17± 5.55 Bq/kg for 226 Ra, 232 Th, 40 K and 137 Cs respectively. The study also examine some radiation hazard indices such as Radium equivalent activity (Raeq), Absorbed gamma dose rate (D), External hazard index (Hex), Internal hazard index (Hin) and gamma index (Iγ). These calculated hazard indices to estimate the potential radiological health risk in soil. The radium equivalent activity average (Raeq) was less than the permitted value (370 Bq/kg). The average absorbed dose rate value also less than the permissible limit of 55 nGy/h. The external hazard index, internal hazard index and gamma index of soil samples were less than unity.

Radioactivity of drilling cuttings from shale resources of the lower paleozoic Baltic Basin

Fractionated drilling wastes originating from shale gas exploration in the Baltic Basin in Polish Pomerania were subjected to measurements of mean activity concentrations of naturally occurring radioactive materials (NORMs). X-ray diffraction (XRD) and scanning electron microscopy (SEM) analyses were used to understand the rock structure and texture. The activity concentration of radionuclides in bulk wastes and fractionated samples (latter obtained through a sieve analysis) was analyzed by using a gamma-ray spectrometer. After fractionation, three different size ranges were distinguished. Radiological indices were estimated by comparison with the levels recommended by the International Association of Oil and Gas Producers (OGP) and an equivalent absorbed dose was determined with respect to appropriated disposal of cuttings. The results showed that the drilling cuttings from the Ordovician period have a natural radioactivity level comparable to other rocks with the same lithology (potassium K-40 800-992 Bq/kg and thorium Th-232 23.3-30.8 Bq/kg) and they did not exceed acceptable levels of the total absorbed dose rate. The average absorbed dose rate in outdoor air one meter above the drilling cuttings was 54.1 nGy/h. The relation between particle size and natural radioactivity indicated that the concentration of radionuclides increased as the fractions size decreased.

The absorbed dose to blood from blood-borne activity

The radiation absorbed dose to blood and organs from activity in the blood is relevant for nuclear medicine dosimetry and for research in biodosimetry. The present study provides coefficients for the average absorbed dose rates to the blood from blood-borne activity for radionuclides frequently used in targeted radiotherapy and in PET diagnostics. The results were deduced from published data for vessel radius-dependent dose rate coefficients and reasonable assumptions on the blood-volume distribution as a function of the vessel radius. Different parts of the circulatory system were analyzed separately. Vessel size information for heart chambers, aorta, vena cava, pulmonary artery, and capillaries was taken from published results of morphometric measurements. The remaining blood not contained in the mentioned vessels was assumed to reside in fractal-like vascular trees, the smallest branches of which are the arterioles or venules. The applied vessel size distribution is consistent with recommendations of the ICRP on the blood-volume distribution in the human. The resulting average absorbed dose rates to the blood per nuclear disintegration per milliliter (ml) of blood are (in 10−11 Gy·s−1·Bq−1·ml) Y-90: 5.58, I-131: 2.49, Lu-177: 1.72, Sm-153: 2.97, Tc-99m: 0.366, C-11: 4.56, F-18: 3.61, Ga-68: 5.94, I-124: 2.55. Photon radiation contributes 1.1–1.2·10−11 Gy·s−1·Bq−1·ml to the total dose rate for positron emitters but significantly less for the other nuclides. Blood self-absorption of the energy emitted by ß-particles in the whole blood ranges from 37% for Y-90 to 80% for Tc-99m. The correspondent values in vascular trees, which are important for the absorbed dose to organs, range from 30% for Y-90 to 82% for Tc-99m.

Measurement of terrestrial gamma radiation dose and evaluation of annual effective dose in Shimoga District of Karnataka State, India

Human beings are continuously exposed to the radiations coming from terrestrial and extraterrestrial sources and inside their own bodies. This study presents the results of indoor and outdoor ambient gamma dose rates in and around granite regions of Shimoga District, and these measurements were carried out by using environmental radiation Dosimeter ER-709 which is a portable detector. By the measured average absorbed dose rates, annual effective dose (AED) has been calculated by a standard method. Results showed that the indoor and outdoor absorbed dose rates in air of Shimoga district ranged between 114.05 ± 2.11 to 332.6 ± 3.99 nGy/h and 87 ± 1.7 to 276.66 ± 4.76 nGy/h. The indoor and outdoor AED ranged between 0.559 to 1.631 mSv/year with an average value of 0.872 mSv/year and 0.106 to 0.339 mSv/year with an average value of 0.235 mSv/year, respectively. The calculated indoor and outdoor AEDs were found to be higher than the world average.

Terrestrial gamma radiation dose measurement and health hazard along river Alaknanda and Ganges in India

Direct measurement of absorbed dose rate in air due to exposure from outdoor terrestrial γ radiation and assessment of consequent public health hazard continues to be of environmental and public concern. Present study was aimed to establish a baseline data of annual effective dose and to assess the associated health risk from outdoor terrestrial γ radiation along the river Alaknanda and Ganges of India. Terrestrial γ radiation exposure doses (excluding cosmic radiation) were measured using a Plastic Scintillation Counter. Absorbed dose rates in air were measured at eight designated locations from Nandprayag to Allahabad along the river. From the average absorbed dose rates, annual effective dose (AED) and excess life time cancer risks (ELCR) were calculated by standard method. Results showed that absorbed dose rates in air ranged between 81.33 ± 2.34 nSv.h−1 and 144 ± 5.77 nSv.h−1 and calculated AED ranged between 0.10 ± 0.012 mSv.y−1 to 0.18 ± 0.007 mSv.y−1 at the designated locations along these rivers. Calculated ELCR were found in the range of 0.375 × 10−3 to 0.662 × 10−3. Present study measured the outdoor γ radiation levels along the rivers. The calculated annual effective doses and life time cancer risk were found higher than the world average value at higher altitudes. But the measured doses and calculated risks at plains were close to that of reported average values.

Measurements of natural gamma radiation in beach sediments of north east coast of Tamilnadu, India by gamma ray spectrometry with multivariate statistical approach

The distribution of natural gamma ray emitting 238U, 232Th and 40K radionuclides in beach sediments along north east coast of Tamilnadu, India has been carried out using a NaI(Tl) gamma ray spectrometric technique. The total average concentrations of radionuclides 238U, 232Th, and 40K were 35.12, 713.16, and 349.60 Bq kg−1, respectively. Correlations made among these radionuclides prove the existence of secular equilibrium in the investigated sediments. The total average absorbed dose rate in the study areas is found to be 504.75 nGyh−1, whereas the annual effective dose rate has an average value of 0.62 mSvy−1. The mean activity concentrations of measured radionuclides were compared with other literature values. The ratios between the detected radioisotopes have been calculated for spatial distribution of natural radionuclides in studied area. Also the radiological hazard of the natural radionuclides content, radium equivalent activity, external hazard index of the sediment samples in the area under consideration were calculated. Multivariate Statistical analyses (Pearson Correlation, Cluster and Factor analysis) were carried out between the parameters obtained from radioactivity to know the existing relations.

Natural radioactivity in sand samples collected along the bank of river Indus in the area spanning over Gilgit to Lowarian, Pakistan: assessment of its radiological hazards

Sand is extensively used in construction of buildings. The presence of natural radioactivity in it results in internal and external exposure to the general public. Therefore, it is desirable to determine the concentration of naturally occurring radio-nuclides, namely 232Th, 226Ra and 40K in sand. In this regard, in continuation of our earlier studies, 42 sand samples were collected from fourteen different locations along the banks of river Indus from Gilgit to Lowarian in the northern part of Pakistan covering an area of ~500 km. In order to measure the specific activities in these samples, a P-type coaxial high purity germanium based gamma-ray spectrometer was used. Average values of the measured activities of 226Ra, 232Th and 40K were found to be 45.6 ± 3, 74.73 ± 3 and 339.8 ± 3.6 Bq kg−1, respectively which results in an average absorbed dose rate 83.54 nGy h−1. From the measured activities, average radium equivalent activity was found to be 178.59 Bq kg−1. External and internal hazard indices were also calculated and found to be 0.48 and 0.61, respectively. Average effective dose expected to be received due to the gamma rays was 0.26 mSv y−1. Measured natural radioactivity, hazard indices and effective doses received by the population were found to be within the recommended limits.

A high spatial resolution outdoor dose rate map of the Rio de Janeiro city, Brasil, risk assessment and urbanization effects

Geophysical surveys have been widely used for geological mapping, and with appropriate ground calibration the database can be converted to radiometric surveys. Herein we present a case study of a high resolution map of the City of Rio de Janeiro, Brazil, constructed by integrating aerial and in situ (ground) measurements. This allowed assessing the influence of urbanization observed between 1978 and 2009 on radiation external exposure. Radiometric, geological and demographics databases were integrated in a Geographic Information System (GIS) facility. The average absorbed dose rate recorded for the city was 96 ± 0.3 nGy h−1 and ranged from 22 to 152 nGy h−1 among districts. The corresponding annual effective dose was determined as 0.09 ± 0.01 mSv. The number of people at risk per year according to the estimated natural radiation levels was 17 ± 1.4, among the 28,000 new cases estimated by the INCA (Brazilian National Cancer Institute) within a population of approximately 6.3 million people.

Measurement of natural radioactivity in soil from Peshawar basin of Pakistan

Natural radioactivity in the environment may change with time due to human activities, chemical and biological changes. From the view of radiation risk to population, the knowledge of natural radioactivity levels and the measurement of collective radiation dose received by the population is very vital. Radiological constraints on soil of thickly populated Peshawar basin in northern Pakistan were assessed through radiometric assay. Soil samples collected from different locations of four districts of this basin were analysed using an HPGe gamma spectrometer. Activity concentrations of 40K, 226Ra and 232Th in these samples was 648 ± 121 (421–996), 45 ± 7 (32–60) and 59 ± 7 (46–72) Bq kg−1, respectively that followed lognormal distribution. The average concentrations of primordial radionuclides were found to be higher than that reported for the worldwide soil. Radium equivalent activity and gamma index derived from these activity concentrations were lesser than their respective limits. The average absorbed dose rate and the annual effective dose for both indoor and outdoor cases were found to be higher than the values given in the UNSCEAR 2000 report. The results of the present study were compared with those for other locations of Pakistan along with that for the world. The radiological impact of the measured data was evaluated using hazard assessment models. A thoughtful discussion of the above mentioned evaluation is also given.

Radioactive Doses Contamination in Al Tuwaitha Nuclear Site, Using GIS Techniques

In this paper, the authors aim to introduce contamination in Al Tuwaitha nuclear site, Iraq using GIS techniques and visual interpretation. This contamination problem draws attention to the new result of high-radiation dose equivalents found in part of the country. The radiation levels in Al Tuwaitha nuclear site, compared with the international standards of UNSCEAR 2000 and world nuclear association (WNA 2011), the absorbed doses in the study area vary between (0.01-140) mrad/hr, in Al Tuwaitha nuclear research center. The maximum radiation dose was nearby the Russian 5 MW reactor. The absorbed dose in Russian 5 MW reactor was about (140) mrad/hr which is the highest hotspot in Al Tuwaitha nuclear research center. The obtained values of the average absorbed dose rate level are exceeding the permitted level by (9500) times higher than environmental levels given by UNSCEAR (2000).

Radionuclides measurements and mineralogical studies on beach sands, East Rosetta Estuary, Egypt

Radiometric measurements were carried out for the beach sands from East Rosetta estuary to determine the activity concentrations of 238U, 226Ra, 232Th, and 40K, using a Hyper Pure Germanium spectrometer, to estimate the dose rates and radiation hazard indices. The average specific activities are 778.20 Bq/kg for 238U; 646.89 Bq/kg for 226Ra; 621.92 and 627.85 Bq/kg for the 222Rn daughters 214Pb and 214Bi respectively. The average specific activity of 232Th is 1510.25 Bq/kg, while the calculated specific activity for 40K has an average of 8.41 Bq/kg. The average specific activity of 235U is 38.61 Bq/kg. The average absorbed dose rate is 1211.36 nGy/h, 20 times higher than the estimated average global primordial radiation of 60 nGy/h and 6 times higher than that of the world range (10–200 nGy/h). The radium equivalent (Raeq) values are from 6 to 9 times the recommended value. The internal and external hazard indices (Hint, Hex) indicate that their values are from 6 to 11 times the permissible values of these indices. These higher values may be due to the presence of economic heavy minerals containing radionuclides as zircon and monazite as well as some trace minerals, thorite and uranothorite. The mineralogical study indicates the beach sands contain heavy minerals, zircon, monazite, rutile, ilmenite, leucoxene, magnetite and garnet. The average abundance of zircon is 0.175 wt% ranging from 0.125 wt% to 0.239 wt%, while it is 0.004wt% ranging from 0.001 wt% to 0.007 wt% for monazite. The average abundance is 0.087 wt% for rutile; 2.029 wt% for ilmenite; 1.084 wt% for magnetite; 0.384 wt% for leucoxene and 0.295 wt% for garnet.