Average annual committed effective dose and threshold consumption rate of bovine samples collected from a government owned abattoir, Ikpoba slope, Benin City, Nigeria

2020 ◽  
Vol 98 (8) ◽  
pp. 742-751
Author(s):  
K.W. Giwa ◽  
O.D. Osahon

The activity concentrations of 40K, 232Th, and 238U in five different organs of bovine meat commonly eaten by the Nigerian populace were measured using gamma ray spectrometry. The meat samples were collected from a Government owned abattoir at Ikpoba slope, Benin City. The essence of the study was to estimate the internal radiation dose incurred by a population due to the ingestion of radionuclides from meat consumption. The mean absorbed dose rate was 12.60 ± 1.51 nGy h−1, which is far lower than the recommended value of 55 nGy h−1. The AACED obtained in this study differs for each organ, thereby making the threshold consumption rate different, but the mean dose, 0.171 ± 0.07 mSv yr−1, is below the 0.3 mSv yr−1 reported to be the recommended average value. The mean threshold consumption rate for meat intake for the samples under study was calculated to be 107.5 ± 6.22 kg yr–1. Thus, this study has contributed to the body of knowledge and data that can lead to the formulation of regulations related to radiological healthcare in the study area.

2020 ◽  
Vol 188 (3) ◽  
pp. 316-321
Author(s):  
Fei Tuo ◽  
Xuan Peng ◽  
Qiang Zhou ◽  
Jing Zhang

Abstract 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 2945 Bq per kg with an average of 127.8, 114.8, and 701.5 Bq 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.


Author(s):  
P.M. Gyuk ◽  
J.O. Anaegbu ◽  
H.O. Aboh ◽  
R. Daniel ◽  
A. Aruwa ◽  
...  

The background radiation of the areas was collected at random for each point using a rados survey meter. The detectors (two rados survey meter were used) were placed 1 meter above the ground with the operator positioned a few meters away. Three (3) readings were taking from each detector in other to reduce error or reach accuracy in obtaining the background readings from each randomly selected point where soil samples were later collected. In the current study, the concentration levels of naturally occurring radioactive materials (NORMs) of 40K, 232Th, and 238U in the surface soil samples of selected areas in kigo road new extension Kaduna north, Kaduna in Nigeria were studied. The collected soil samples were analyzed by means of gamma-ray spectrometry. The mean activity concentrations of the natural occurring radionuclides of  226Ra, 232Th and 40K in the soil samples were estimated to be 62, 78.35, 227.17 Bq/kg respectively for kigo road new extension respectively. Radium equivalent activity, absorbed dose rate, annual effective dose equivalent were also calculated for assessment of radiological risk. External hazard value (Hex) is between 0.3163 and 0.9557 and Internal hazard value is between 0.4462 and 1.1618. The worldwide average activity concentrations of 226Ra, 232Th and 40K in soil samples from various studies around the world have values of 37, 30 and 400 Bq/kg respectively [UNSCEAR, 2000]. The values compared well with published data from UNSCEAR shows Ra-226, Th-232 from the location are well above the standards while K-40 below the risk value.


2020 ◽  
Vol 43 (2) ◽  
pp. 169-180
Author(s):  
Md Samiul Ehsan ◽  
Md Faisal Rahman ◽  
Nafisa Tabassum ◽  
Md Mahidul Haque Prodhan ◽  
Shikha Pervin ◽  
...  

The study has been carried out to measure the activity concentration of natural and anthropogenic radionuclides in fifteen(15) soil samples of Natore, Kushtia and Pabna district, which are around the 30 km peripheral area of Rooppur Nuclear Power Plant, by gamma ray spectrometry system using a High Purity Germanium (HPGe) detector. It is found that the activity concentration of 226Ra, in the collected sample was from 3.52 Bq/kg to 28.5 Bq/kg with the average value of 12.42 Bq/kg. For 232Th, the range was from 4.18 Bq/kg to 34.5 Bq/kg with the average value of 12.6 Bq/kg. Finally, the activity concentration of 40K, in the collected sample was in the range of 84 Bq/kg to 345 Bq/kg, and the average value was 198.9 Bq/kg. The absorbed dose rate (D) was found to be in the range of 4.59 nGy/h to 40.93 nGy/h with the mean value 21.3 nGy/h. The annual effective dose (E) was in the range of 0.006 mSv/yr to 0.152 mSv/yr with an average of 0.033 mSv/yr. The radium equivalent activity was in the range from 10.02 Bq/kg to 89 Bq/kg with an average of 44.99 Bq/kg. The external hazard index (Hex) was found to be in the range of 0.027 to 0.242 with the mean value of 0.121 and the internal hazard index (Hin) was found to be in the range of 0.044 to 0.302 with the mean value of 0.156. All the values are much below the recommended limit by the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR), 35 Bq/kg for 226Ra, 30 Bq/kg for 232Th and 400 Bq/kg for 40K. According to international and national regulation, the annual dose to members of the public, 1 mSvy-1 and Hex & Hin must be lower than unity. Moreover, no artificial radioactivity was found in the soil samples of this study area. This research concludes that the found values are within the permissible limits as required by the Nuclear Safety and Radiation Control(NSRC) Rules-1997 of Bangladesh and International Atomic Energy Agency(IAEA) Safety Standards- General Safety Requirements (GSR): Part-3. Journal of Bangladesh Academy of Sciences, Vol. 43, No. 2, 169-180, 2019


2005 ◽  
Author(s):  
J M Carson ◽  
P B Holman ◽  
K L Ford ◽  
J A Grant ◽  
R B K Shives

2003 ◽  
Author(s):  
J M Carson ◽  
P B Holman ◽  
K L Ford ◽  
J A Grant ◽  
R B K Shives

2009 ◽  
Vol 24 (1) ◽  
pp. 56-60 ◽  
Author(s):  
Abdul Jabbar ◽  
Arshad Bhatti ◽  
Syed Ahmad ◽  
Waheed Arshed ◽  
Perveen Akhter

Environmental gamma radiation levels in northern Rechna Doab, Pakistan, were measured as a part of systematic study aimed at the establishment of the background data base of radiation and radioactivity levels. The measurements reported in this paper were made with portable radiation monitor which employed GM tube and was calibrated against secondary standard dosimetry system. The average absorbed dose rate in air was determined to vary from 86.0 nGy/h to 139.1 nGy/h with the mean value of 109.1 nGy/h. The annual effective dose remained within the range of 105.47 mSv to 170.54 mSv with its average value of 133.73 mSv. These environmental radiation doses in the area were comparable with those reported for other countries. It was concluded that the prevalent radiation levels did not pose any significant radiological health hazard to the population.


2016 ◽  
Vol 31 (2) ◽  
pp. 190-194 ◽  
Author(s):  
Sukai Zhuang ◽  
Xinwei Lu ◽  
Jiantao Li ◽  
Qian Li

The radiation hazards of five kinds of different solid metallic tailings collected from Shangluo, China were determined on the basis of natural radioactivity measurements using low background multichannel gamma ray spectrometry. The activity concentration of 226Ra, 232Th and 40K in the tailings ranged from 5.1 to 204.3, 3.8 to 28.5, and 289.6 to 762.3 Bq/kg, respectively. The radium equivalent activities and the external hazard indexes of all studied metallic tailings were below the internationally accepted value of 370 Bq/kg and unity, respectively. The internal hazard index of vanadium tailings exceeded unity, while the internal hazard indexes of other analyzed metallic tailings were less than unity. The indoor air absorbed dose rate values for all studied metallic tailings except lead-zinc tailings and gold tailings were higher than the world population-weighted average of 84 nGy/h and the annual effective dose values of all metallic tailings except for vanadium tailings were lower than 1 mSv. The study showed that vanadium tailings present a radiation hazard and their usage as building materials should be restricted.


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