scholarly journals Monitoring of Background Radiation in Selected Schools in Ota, Ogun State Nigeria by Direct Measurement of Terrestrial Radiation Dose Rate

Author(s):  
C. A. Onumejor ◽  
A. Akinpelu ◽  
T. E. Arijaje ◽  
M. R. Usikalu ◽  
O. F. Oladapo ◽  
...  
2021 ◽  
Vol 5 (1) ◽  
pp. 524-528
Author(s):  
I. A. Bello ◽  
O. O. Ige ◽  
N. Kure ◽  
A. H. Momoh

Background radiation involves the measure of the level of ionizing radiation present in the environment at a particular location. This research seek to generate data of the natural background radiation level of some selected Sections at Kabba College of Agriculture, using RadEye G20 survey meter. A total of 15 sections of the College were randomly selected and the background radiation dose rate of the sections were measured. The indoor dose rate ranged from (0.09 – 0.13) 𝜇Sv/yr, while the outdoor dose rate ranged from (0.07 - 0.10) 𝜇Sv/yr. The indoor annual effective  dose were observed to be greater than the outdoor annual effective dose in all the College Sections measured. The lowest total annual effective dose 0.75 𝑚𝑆𝑣/𝑦𝑟 was found at the Academic staff block. The highest total annual effective dose of 1.09 𝑚𝑆𝑣/𝑦𝑟 was found at the livestock building, this might be due to the high-altitude nature of the area and the rocky materials used in the construction of the building. The highest total annual effective dose of the study area was slightly above the recommended limit of 1.0 𝑚𝑆𝑣/𝑦𝑟. The result obtained from this research may not constitute immediate health risk to the staff and student of the college


2009 ◽  
Vol 1 (2) ◽  
Author(s):  
Ahmad Termizi Ramli ◽  
Nursama Heru Apriantoro ◽  
Husin Wagiran ◽  
A Kholik Wood ◽  
Lee Siak Kuan

2015 ◽  
Vol 6 ◽  
pp. 145-149
Author(s):  
F Gbaorun ◽  
D Terver

In this study, a Geiger Muller ionization counter has been used to investigate the variation of background radiation dose level with time in a typical x-ray machine room and its environment. This is to monitor the effect of x-ray exposure on the background ionizing radiation level. The results showed that within a period of 3 hours, the cumulative background radiation dose in the x-ray room grew from s s Gy to around 84 . 90 ́ 10 - 10 - an initial level of 38 . 78 ́ Gy compared with nearby rooms where the s cumulative radiation grew from almost zero to a maximum value of about 46 . 9 ́ Gy within the 10 - same period. It was observed that after a radiation exposure from the machine, the background s radiation dose rate took about 25 minutes to decay from a maximum level of around 45 ́ Gy/hr to 10 - - s 17 . 47 ́ 10 the background level about Gy/hr which was found to be higher than the background dose rates in other nearby locations. While the dose rate in the x-ray machine room was higher than the s 10 - maximum dose limit of 12 ́ Gy/hr recommended for members of the public by the International Committee for Radiation Protection (ICRP), the dose rates in the other locations studied in the neighbourhood of the x-ray machine were within the limit.


2017 ◽  
Vol 156 ◽  
pp. 00006
Author(s):  
A. Izham ◽  
A.T. Ramli ◽  
W.M. Saridan Wan Hassan ◽  
H.N. Idris ◽  
N.A. Basri

2009 ◽  
Vol 14 (3) ◽  
pp. 85-88 ◽  
Author(s):  
Mariusz GRUDA ◽  
Grażyna KOSICKA ◽  
Ewelina KONSTANTY ◽  
Dariusz KOWALCZYK

Author(s):  
Amir Hamzah ◽  
Hery Adrial ◽  
Subiharto Subiharto

EVALUATION OF RADIATION DOSE RATE OF RSG-GAS REACTOR. The RSG-GAS reactor has been operated for 30 years. Since the nuclear reactor has been operated for a long time, aging process on its components may occur. One important parameter for maintaining the safety level of the RSG-GAS reactor is to maintain radiation exposure as low as possible, especially in the working area. The evaluation results should be able to demonstrate that the radiation exposure of the RSG-GAS is still safe for workers, communities and the surrounding environments. The purpose of this study is to evaluate radiation exposure in the working area to ensure that the operation of RSG-GAS is still safe for the next 10 years. The scope of this work is confirming the calculation results with the measured radiation dose in the RSG-GAS reactor working area. Measurement of radiation exposure is done by using the installed equipments at some points in the RSG-GAS working area and a portable radiation exposure measurement equipment. The calculations include performance of a modeling and analysis of dose rate distribution based on the composition and geometry data of RSG-GAS by using MCNP.  The analysis results show that the maximum dose rate at Level 0 m working area of RSG-GAS reactor is 3.0 mSv/h with a deviation of 6%, which is relatively close to the measurement value. The evaluation results show that the dose rate in RSG-GAS working area is below the limit value established by the Nuclear Energy Regulatory Agency of Indonesia (BAPETEN) of 10 mSv/h (for the average effective dose of 20 mSv/year). Therefore, it is concluded that the dose rate in RSG-GAS working area is safe for personnel..Kata kunci: dose rates, RSG-GAS, radiation safety, MCNP.


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