scholarly journals Remote radiation monitoring device

2020 ◽  
Vol 1614 ◽  
pp. 012108
Author(s):  
V A Kulikova ◽  
V V Yakovlev ◽  
A Yu Tumanov ◽  
V A Tumanov ◽  
A V Kulinkovich
2008 ◽  
Vol 45 (sup5) ◽  
pp. 414-416 ◽  
Author(s):  
Shin-ichi Okuyama ◽  
Tatsuo Torii ◽  
Akihiko Suzuki ◽  
Masanori Shibuya ◽  
Nobuyuki Miyazaki

2021 ◽  
Vol 9 (1) ◽  
pp. 23-31
Author(s):  
Mohammed Belayet Hossain ◽  
Dr. Mohammad Sohelur Rahman ◽  
Dr. Mohammad Amir Hossain Bhuiyan ◽  
Selina Yeasmin

Objective: The pollution free environment is required for healthy life. The real-time radiation monitoring is very important for radiation hazard detection in the environment. The excess life-time cancer risk (ELCR) on public is to assess based on the real-time radiation monitoring data in the area. Methods: The real-time radiation monitoring was performed using portable digital radiation monitoring device. This real-time digital portable radiation monitoring device meets all European CE standards as well as the American “FCC 15 standard”. The real-time digital portable radiation monitoring device was placed at 1 meter above the ground on tripod and data collection time for each monitoring point (MP) was 1 hour. 27 MPs were chosen for collection of real-time radiation data at various outdoor environment in Motijheel Thana, Dhaka from May-August 2018.Results: The real-time radiation dose rates at Motijheel Thana due to natural radionuclides were ranged from 0.095 ± 0.041 µSv.h-1 to 0.185 ± 0.042 µSv.h-1 with an average of 0.147 ± 0.047 µSv.h-1. The annual effective dose to public from outdoor environmental radiation at Motijheel Thana were found to be 0.166 ± 0.066 mSv to 0.324 ± 0.061 mSv with an average of 0.257 ± 0.039 mSv. Excess Life-time Cancer Risk (ELCR) on public are also estimated based on annual effective dose that is ranged from 0.662 ×10-3 to 1.289 ×10-3 with an average value of 1.025 ×10-3, which is higher than world average value of 0.29×10-3. Conclusion: This type of study is required for detection of the radiation hazard arising from the natu-ral as well as man-made sources and also for generation of the baseline database. From this study, it is observed that there is no pose any radiation hazard in the study area due to man-made sources.


2017 ◽  
Vol 90 (3-4) ◽  
pp. 437-442 ◽  
Author(s):  
V. Burtniak ◽  
Yu. Zabulonov ◽  
M. Stokolos ◽  
L. Bulavin ◽  
V. Krasnoholovets

2020 ◽  
Vol 8 (1) ◽  
pp. 9-15
Author(s):  
Faria Hassan ◽  
M. S. Rahman ◽  
Shafi M Tareq ◽  
S. Yeasmin

Objective: Medical institution uses ionizing radiation for diagnosis or treatment by using ionizing radiation generating equipment such as X-ray machines, CT, PET scan, etc. and radioactive materials especially in nuclear medicine centers. The purpose of the study is to monitor the real-time radiation around the Bangabandhu Sheikh Mujib Medical University (BSMMU) campus of Bangladesh for minimizing the ionizing radiation hazard on public health and the environment. Method: The radiation monitoring was performed using a real-time portable digital radiation monitoring device. This real-time digital portable radiation monitoring device meets all European CE standards as well as the American “FCC 15 standard”. The portable radiation monitoring device was placed at 1 meter above the ground on the tripod and data acquisition time for each monitoring point (MP) was 1 hour. 32 MPs were selected for the collection of radiation dose rates around the BSMMU campus from March-May 2019. Results: The measured dose rate around the BSMMU campus ranged from 0.02-3.15 µSv/hr with an average of 1.452 ± 0.883 µSv/hr. The annual effective dose was ranged from 0.117 ± 0.058 mSv to 5.445 ± 0.045 mSv with an average of 2.54 ± 1.566 mSv. The excess lifetime cancer risk (ELCR) was estimated which ranged from 4×10ˆ-4 to 2×10ˆ-2 with an average value of 1×10ˆ-2 for 32 selected locations around BSMMU campus. Conclusion: Dose monitoring helps to ensure the best possible protection of the radiation workers, patients, and the general public and provides an immediate indication of incorrect use of technical parameters or equipment malfunction. Not only that, but it is also essential to use an adequate amount of protective shielding for minimizing radiation hazard on public health and the environment from the scattering radiation of the hospital.


2015 ◽  
Vol 42 (6Part26) ◽  
pp. 3537-3537
Author(s):  
S Taneja ◽  
L Che Fru ◽  
V Desai ◽  
J Lentz ◽  
C Lin ◽  
...  

Author(s):  
Sidratul Moontaha ◽  
Dr. Mohammad Sohelur Rahman ◽  
Dr. Md. Shafiqul Islam ◽  
Selina Yeasmin

Background: In this study, outdoor environmental gamma radiation dose rates were measured at area of Shahbag Thana under Dhaka city and Atomic Energy Research Establishment (AERE) Campus at Savar. Aim of the study: This kind of study is required to detect the presence of natural and artificial radionuclides (if any) releasing from nuclear and radiological facilities in the country or from neighbouring countries. Materials and Methods: The measurement was performed using a real-time portable radiation monitoring device from August-November 2017. The real-time portable radiation monitoring device was placed on tripod at 1 meter above the ground and data acquisition time for each monitoring point (MP) was 1 hour. Total 34 MP were selected around major nuclear and radiological facilities in Bangladesh for collection of dose rate due to gamma-ray. The MPs were marked-out using Global Positioning System (GPS) navigation. The GPS reading of the sampling locations were varied from E90º23'40.08" to E90º24'32.82" and from N23º44'58.62" to N23º43'26.58" for Shahbag Thana and from E90º16'26.58" to E90º16'50.52" and from N23º57'12.96" to N23º57'6.12" for AERE Campus, Savar. Results: The measured dose rates due to natural radionuclides were ranged from 0.105 ± 0.036056 μSv.h-1 to 0.208065 ± 0.106377μSv.h-1 with an average of 0.141568 ± 0.046995 μSv.h-1. The annual effective dose to the population from outdoor environmental gamma radiation was varied from 0.128772 ± 0.044218 mSv to 0.25517 ± 0.130461 mSv and the mean was found to be 0.17362± 0.057635 mSv. This value is lower than some countries like India, China, Sweden, Italy and Czech Republic; and higher than Canada, Mexico, Indonesia, Korea, Turkey, Finland, Spain and some other countries. Conclusion: From this study, it was observed that there is no burden of population exposure due to man-made sources. Therefore, it can be concluded that adequate safety and radiation protection of nuclear & radiological facilities had been ensured which is required for minimizing of unnecessary exposure to populations from man-made sources. The estimated mean annual effective dose found in this study is not expected to contribute significant additional hazard from the radiological health point of view.


2005 ◽  
Vol 1276 ◽  
pp. 422-423 ◽  
Author(s):  
Shinichi Okuyama ◽  
Tatsuo Torii ◽  
Yasunori Nawa ◽  
Ikuo Kinoshita ◽  
Akihiko Suzuki ◽  
...  

1978 ◽  
Vol 44 (4) ◽  
pp. 423-424 ◽  
Author(s):  
V. V. Pevtsov ◽  
V. I. Shipilov ◽  
V. G. Korotkov ◽  
A. N. Filippov

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