Contamination and Radionuclides Concentration in Imported Canned Foodstuffs in Baghdad Markets

Author(s):  
Abdul Jabbar Abbas Oudah ◽  
Asia H. Al-Mashhadani

This work was concerned with study the contamination and concentration of natural and man-made radioactivity 40K, 137Cs, 214Bi (238U series) and 228Ac (232Th series) in 19 different imported foodstuffs canned samples (Mushrooms, Black Olives, Broad Beans, Peaches, Sweet Corn, Tomato Past, Green Peas, Chick Peas, Baby milk 1,2,3 and Full milk powder) , were collected from locally markets in different regions in Baghdad city. Samples were analyzed by high-purity germanium (HPGe) detector gamma spectrometer systems from Canberra, with high resolution (2.0 keV at 1332 keV) and relative efficiency of ~30% for 137Cs (661.7 keV) and provide (Software Genie 2000 from Canberra). From the data obtained, the activity concentrations (Bq/kg or Bq/l) for 40K, 137Cs, 214Bi and 228Ac in above foodstuff samples were measured. It was found that these values lie within the worldwide range for radioactivity in food. The mean value of radium equivalent activity (Raeq) in all samples it was below the threshold value of 370 Bq/kg. The all value of indoor and outdoor annual effective dose equivalent in samples it was lower than the world average values (0.45 mSv/y for indoor and 0.07 mSv/y for outdoor).

The problem of automatic pattern classification in real metallographic images from the steel plant ArcelorMittal Ostrava is addressed. The goal is to monitor the process quality in the steel plant. In the images of metal, there are dark dots that are produced by imperfections along the central axis of each plate. It is necessary to determine automatically the number and sizes of these dots. The number and sizes of the dots is a measure of how imperfect each plate is. The process is presented that segments the area of plates that contains segregation, identifies those rows of pixels along which the dots lie, and counts the pixels that are marked as dots by evaluating all the vertical columns of pixels that intersect the rows that contain the dots. The threshold value is set to be 95% of the mean value of grey scale for each column of pixels and makes the dots white. White dots that are most likely noise are removed to identify dots that are smaller than 4 connected pixels across. The explanations related to the obtained results are firmly related to the information provided by human experts.


2021 ◽  
pp. 15-22
Author(s):  
Milena Živković ◽  
Nenad Zlatić ◽  
Dragana Krstić ◽  
Milan Stanković

In the present work, we determined activity concentrations of ten Medicinal herbs using gamma spectrometry. The radioactivity concentration of 226 Ra, 232 Th, 40 K and 137 Cs were 2.82, 0.63, 984.32, 0.28 Bq/kg, respectively. These doses are not hazardous to the general public's health. The mean values of radium equivalent activity (Raeq), absorbed dose rates (D), annual effective dose (De) and external hazard index (Hex) are 79.51 Bq/kg, 42.73 nGy-1 , 52.40 µSv and 0.21, respectively. Medicinal plants used to make tea do not contain a concentration of tested radionuclides that would cause negative consequences to one's health.


2012 ◽  
Vol 27 (4) ◽  
pp. 392-398 ◽  
Author(s):  
Saeed Rahman ◽  
Muhammad Rafique

Radioactivity levels in building materials, collected from the Islamabad capital territory have been determined by using a gamma spectrometric technique. Measured specific activities of 226Ra, 232Th, and 40K in material samples ranged from 8 ? 1 to 116 ? 6 Bq/kg, 9 ? 1 to 152 ? ? 5 Bq/kg, and 29 ? 6 to 974 ? 23 Bq/kg, respectively. The radium equivalent activity, absorbed dose rate, annual effective dose, and gamma index were evaluated from the measured amounts of radioactivity to assess the radiation hazard associated with the studied building materials. The mean radium equivalent activity, the absorbed dose rate and annual effective dose estimated ranged from 81 ? 6 to 221 ? 11 Bq/kg, 38 ? 3 to 104 ? 5 nGy/h, and 0.23 ? 0.02 to 0.64 ? 0.03 mSv, respectively. The ranges of the calculated Raeq were found to be lower than the values recommended for construction materials (370 Bq/kg). The mean values of the internal and external hazard indices were found in the range of 0.30 ? 0.02 to 0.78 ? 0.05 and 0.22 ? 0.02 to 0.60 ? 0.03, respectively. The results of the materials examined indicate no significant radiological hazards arise from using such material in building construction.


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


2017 ◽  
Vol 140 (2) ◽  
Author(s):  
Mindong Lyu ◽  
Tao Liu ◽  
Zixi Wang ◽  
Shaoze Yan ◽  
Xiaohong Jia ◽  
...  

During touchdowns of active magnetic bearings (AMB), the violent collision between rotors and touchdown bearings (TDB) can cause damages to both parts. Orbit response recognition provides a way for the AMB controller to automatically switch the control algorithm to actively suppress the rotor–TDB vibration and promptly relevitate the rotor during touchdowns. A novel method based on Hilbert transform (HT) is proposed to recognize the orbit responses (pendulum vibration, combined rub and bouncing, and full rub) in touchdowns. In this method, the rotor suspension status is monitored by the AMB controller in real-time. When touchdown is detected, the rotor displacement signal during the sampling period is intercepted, and the instantaneous frequency (IF) is calculated by HT. Then, the local variance of IF during the sampling period is calculated, and it is compared with the threshold value. Combined rub and bouncing can be identified for it has the largest local variance. Finally, the mean value of IF during the sampling period is calculated and is compared with the other threshold value. Pendulum vibration can be identified for it has a lower and fixed mean value, while full rub has a larger value. The principle of the recognition method is demonstrated by the simulated results of a thermo-dynamic model. The results reveal that the method is feasible in recognizing the orbit responses and can be implemented in the AMB controller to help switch the control algorithms automatically in case of touchdowns.


Author(s):  
Asdar Iswati ◽  
Lilik Tri Indriyati

<p>Most of agricultural lands in Pasir Eurih Village are paddy field simple irrigation system, while most of them in Sukajadi Village are upland. Farmers in both villages are used to composting organic residues, but the composts was not used maximally. The aim of the IbM activities was: (1) To guide our partners to produce better quality of composts sustainable; and(2) To motivate the community of peasant  using composts for their farm. The best compost resulted by IbM-3 guidance was made from rice straw, leaf litter, and chicken manure mixed with rice husk as their bedding by ratio of 3:2:1:1. This compost contained macronutrients (N, 0.56%, P<sub>2</sub>O<sub>5 </sub> 1.09%, K<sub>2</sub>O 1.44%, Ca 5.72%, Mg 0.43%, and Na 0.08% respectively), micronutrients Fe 5.309 ppm, Mn 342 ppm, Cu 42 ppm, Zn 69 ppm, and B 33 ppm respectively), and heavy metals of Pb was 4.8 ppm and Cd 0.04 ppm. The addition of 3-4 ton/ha of this compost into paddy soil could reduce chemical fertilizers up to 50%. The addition of 3 ton/ha of this compost to upland soil planted by sweet corn produce same with application of chicken manure bedding or goat manure. Socialization of the benefit of using compost in increasing the soil fertility and crop yield have raised the peasant’s knowledge. It was showed by the mean value of this post test raised 19.67 points for fertilizer and soil fertility matter and 16.63 points for organic materials or natural fertilizers matter.</p><p> </p>


2020 ◽  
Vol 10 (1) ◽  
pp. 11-15
Author(s):  
Samjhana Khadka ◽  
Anamika Jha ◽  
Ranjit Kumar Chaudhary ◽  
Shanta Lall Shrestha

Introduction: Mammography is one of the most commonly performed radiological investigations for evaluation of breast cancer. As it involves ionizing radiation, there remains a risk of radiation induced cancer. In this study, we evaluated compressed breast thickness (CBT) and mean glandular dose (MGD) during routine mammography. Methods: This prospective study was performed in the Department of Radiology and Imaging of TUTH. Data of 500 consecutive patients who underwent mammography over a period of 4 months (June 2018 to September 2018) was collected. The age, CBT and MGD were recorded. Pearson correlation and paired-t tests were performed. Results: Most of the patients belonged to 41-50 years age group. MGD was significantly higher in patients with increased CBT. The CBT and MGD was higher in MLO view compared to CC views. The mean value of total MGD for four views was 5.1±1.4 mGy. There was significant positive correlation (r= 0.517) between CBT and MGD with increase in MGD with increase in CBT. Conclusions: The MGD and dose equivalent in our routine mammography is within the recommended limits. MGD increases with increasing CBT and vice-versa. Hence, decreasing the thickness of compressed breast, can decrease the amount of radiation absorbed by the glandular tissue of the breast.  


2012 ◽  
Vol 160 ◽  
pp. 373-376
Author(s):  
Yu Hua Dong ◽  
Xin Ming Zhou

A difference method to order decision for least square in trend fitting is proposed in this paper. When the least square is used for fitting trend, choosing the proper order is important for trend fitting accuracy. We can use difference n times to obtain difference result data, and the mean value can be taken as decision criteria. Comparing with the threshold value, when the mth difference result mean is smaller, the trend fitting order for least square can be set to m. Simulation processing results show that this method resolve the problem of order decision for least square in trend fitting, and the method has high accuracy for trend extraction.


1988 ◽  
Vol 29 (4) ◽  
pp. 481-485 ◽  
Author(s):  
R. Havukainen

The radiation dose exposure, and the faults in about 1700 dental units inspected at dental surgeries by the Finnish Centre for Radiation and Nuclear Safety in 1981–1985, were analysed. The mean value of skin doses in the bite-wing projection was about 6.2 mGy, the range 0.5 to 151 mGy. The mean energy imparted per bite-wing examination was estimated as 0.68 mJ and that per panoramic examination as 1.2 mJ. That gives a total imparted energy of about 600 J per year for conventional dental examinations and about 420 J per year for panoramic examinations. This gives a total of 0.13 mJ from conventional and 0.089 mJ from panoramic examinations per inhabitant per year. The collective effective dose equivalent was calculated as about 9 manSv for conventional dental examinations and about 6 manSv for panoramic examinations. Twenty per cent of units had some fault which was capable of decreasing radiation safety. Forty per cent of units were served reparation orders or other remarks were made in inspection documents. Large doses were usually accounted for by incorrect film processing and malfunction of the exposure timer.


Author(s):  
U. Rilwan ◽  
I. Umar ◽  
G. C. Onuchukwu ◽  
H. A. Abdullahi ◽  
M. Umar

This work evaluates the radiation hazard indices from some selected mining sites in Nasarawa West, using Sodium Iodide Thallium Gamma Spectrometry. Raeq ranged from 100.39-197.40 Bq/Kg with a mean 161.44 Bq/Kg, which is lower than the average of 370 Bq/Kg. The GADR ranged from 44.85 nGy/hr-90.71 nGy/hr with the mean 73.68 nGy/hr. which is also below the average of 89 nGy/hr for soil. The AGED ranged from 315.77 mSv/yr-640.91 mSv/yr with the mean 519.19. Which is above the threshold value of 300 mSv/yr. ACI ranged from 0.73-1.45 with the mean value 1.18 which is above the standard of unity. The AEDE (outdoor) ranges from 0.055 mSv/yr-0.111 mSv/yr with the mean 0.090 mSv/yr which is above the 0.07 mSv/yr standard permissible limit. The AEDE (indoor) ranged from 0.220 mSv/yr-0.445 mSv/yr, with the mean value 0.361mSv/yr. This is below the 0.45 mSv/yr threshold. The ELCR ranged from 00.770-1.558 with the mean value 1.265 and from 0.193-0.389 with the mean value 0.317 for outdoor and indoor respectively, which exceed the 0.29 X 10-3 threshold limit. The External  and  Internal  Hazard  indices ranges from 0.271-0.533 and 0.289-0.675 as well as mean values 0.435 and 0.512 respectively, which are  below the threshold. Therefore, there may be serious radiological effects to the populace.


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