The effective dose to the public of Kerman province from gamma emitter terrestrial radionuclides

2009 ◽  
Vol 6 (1) ◽  
pp. 1
Author(s):  
S. Hafezi ◽  
A. Shokraei ◽  
H. Sajadi ◽  
A. Najafi
Keyword(s):  
Effective Dose ◽  
The Public ◽  
Terrestrial Radionuclides ◽  
Gamma Emitter

scholarly journals EXPOSURE OF THE PUBLIC OF THE LENINRGAD REGION DUE TO THE NATURAL SOURCES OF IONIZING RADIATION

2018 ◽  
Vol 11 (2) ◽  
pp. 91-97 ◽  
Author(s):  
O. A. Istorik ◽  
L. A. Eremina ◽  
A. N. Barkovsky ◽  
T. A. Kormanovskaya ◽  
R. R. Akhmatdinov
Keyword(s):  
Ionizing Radiation ◽  
Effective Dose ◽  
Residential Buildings ◽  
Beta Activity ◽  
Leningrad Region ◽  
Volume Activity ◽  
Radiation Dose Rate ◽  
Natural Sources ◽  
The Public ◽  
The Individual

This study is focused on the analysis of the results of the radiation-hygienic passportisation and the Joint state system of control and accounting of the individual doses of the public from natural sources of ionizing radiation in the Leningrad region. The results of the study include data on the number of measurements of the gamma-radiation dose rate in buildings and in open territories, number of measurements of volume activity and equivalent equilibrium volume activity of radon in the air in the public and residential buildings in the Leningrad region in 2007–2016 as well as the number of the assessments of the total volume alpha and beta activity and concentration of the natural occurring radionuclides in drinking water. The authors performed an assessment of the annual individual effective dose per resident of theLeningradregion. It was estimated as 3.09 mSv/year considering all the data in Regional dose databank. Natural sources of ionizing exposure contribute 92.6% to the annual effective dose to the public of the Leningrad region, that exceeds the average Russian values by 6%.

scholarly journals Assessment of Radiation Risk on Healthcare Workers and Public in & around Two Largest Hospital Campuses of Bangladesh

2021 ◽  
pp. 48-57
Keyword(s):  
Public Health ◽  
Effective Dose ◽  
Healthcare Workers ◽  
Radiation Risk ◽  
Radiation Monitoring ◽  
Radiation Hazard ◽  
Lifetime Cancer Risk ◽  
The Public ◽  
Continuous Radiation ◽  
Yearly Effective Dose

Ionizing radiation gives tremendous benefit to mankind in the hospital through diagnosis and treatment to patients but unnecessary radiation may cause harm to healthcare workers & the public. The purpose of the study is to continuous radiation monitoring in & around the three largest radiological facilities of Bangladesh such as Atomic Energy Centre Dhaka (AECD), Dhaka Medical College Hospital (DMCH) & Bangabandhu Sheikh Mujib Medical University (BSMMU) campuses, and estimation of radiation risk on healthcare workers & public health. Continuous radiation monitoring was performed in & around the AECD, DMCH, BSMMU campuses from August-October 2020 using the Chemiluminescent Dosimeters. The yearly effective doses to healthcare workers and the public due to radiation released from the facilities were ranged from 0.606 ± 0.031 mSv to 0.801 ± 0.0.042 mSv with a mean of 0.707 ± 0.053 mSv. The excess lifetime cancer risk (ELCR) on healthcare workers & public health were evaluated based on the yearly effective dose and ranged from 2.486 Χ 10-3 to 3.287 Χ 10-3 with a mean of 2.900 Χ 10-3. The average yearly effective dose and ELCR on healthcare workers & public health were lower than those of the worldwide permissible values. Continuous radiation monitoring in & around the largest radiological facilities is required for detection of the radiation generating equipment’s malfunctions and improper handling of the radioactive materials. The study would help for minimization of radiation risk on healthcare workers & the public and this keeps the hospital’s environment free from radiation hazard.

scholarly journals Analysis on radiation control and the impact of land pipeline leakage of offshore nuclear power plant on groundwater

2021 ◽  
Vol 2083 (2) ◽  
pp. 022021
Author(s):  
Lianghui Liu ◽  
Jiahuan Yu ◽  
Yueping Xu
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Effective Dose ◽  
Nuclear Power ◽  
Annual Effective Dose ◽  
Radionuclide Concentration ◽  
The Public ◽  
Radiation Control ◽  
Land Drainage ◽  
The Impact

Abstract Using the groundwater migration and dispersion analytical model, combined with the topography and groundwater characteristics along the land drainage pipeline of an offshore nuclear power plant, the migration and dispersion of six radionuclides (3H, 14C, 137Cs, 134Cs, 60Co, 90Sr, etc.) in groundwater under the condition of pipeline breach accident are predicted. The scope of impact of radionuclides and the annual effective dose caused by drinking water pathways to the public are analyzed. By summarizing the radionuclide concentration and dose index requirements for groundwater at home and abroad, the corresponding environmental impact assessment is given. The prediction results show that the radionuclide concentration and public effective dose at the same distance first increase and then decrease with time, and the peak radionuclide concentration and maximum public effective dose gradually decrease with distance increasing, in other words, the impact of the breach accident on the distance above 30 m is limited.

scholarly journals Radiological consequences assessment of a hypothetical accident during transportation of spent nuclear fuel

2019 ◽  
Vol 34 (1) ◽  
pp. 94-101
Author(s):  
Bo Cao ◽  
Weijie Cui
Keyword(s):  
Effective Dose ◽  
Effective Dose Equivalent ◽  
Nuclear Fuels ◽  
Dose Equivalent ◽  
The Public ◽  
Hypothetical Accident ◽  
Ground Deposition ◽  
Total Effective Dose Equivalent ◽  
Reprocessing Plant ◽  
Total Effective Dose

During the transportation of spent nuclear fuels, the potential release of the radioactive materials into the atmosphere in the case of an accident becomes a serious threat to public health and the environment. In China, a commercial reprocessing plant is planned to be commissioned around 2025 based on the China nuclear roadmap. After being cooled on site the spent nuclear fuels are transported to the reprocessing plant by train or truck. This requires the assessment of radiological consequences of such accidents during transportation, therefore dose calculations under hypothetical accident conditions have been presented in this paper. The total effective dose equivalent and ground deposition are calculated using the HotSpot health physics computer code with site-specific meteorological conditions. The results indicate that the total effective dose equivalent and ground deposition are both decreased with the increase of the downwind distance. The maximum of the total effective dose equivalent is about 1.4?101 Sv, which is larger than the regulation limit for the public. The TEDE counter plot shows that the inner regions marked with dose contours of 1.0?10?3 Sv are higher than the regulation limits for the public, however this needs no intervention but any unnecessary trip to this area should be avoided.

scholarly journals It's Time for a New Low-Dose-Radiation Risk Assessment Paradigm—One that Acknowledges Hormesis

Dose-Response ◽  
2007 ◽  
Vol 6 (4) ◽  
pp. dose-response.0 ◽  
Author(s):  
Bobby R. Scott
Keyword(s):  
Risk Assessment ◽  
Radiation Exposure ◽  
Effective Dose ◽  
Radiation Protection ◽  
Current System ◽  
Equivalent Dose ◽  
Exposure Limits ◽  
The Public ◽  
Nuclear Workers ◽  
Radiation Induced

The current system of radiation protection for humans is based on the linear-no-threshold (LNT) risk-assessment paradigm. Perceived harm to irradiated nuclear workers and the public is mainly reflected through calculated hypothetical increased cancers. The LNT-based system of protection employs easy-to-implement measures of radiation exposure. Such measures include the equivalent dose (a biological-damage-potential-weighted measure) and the effective dose (equivalent dose multiplied by a tissue-specific relative sensitivity factor for stochastic effects). These weighted doses have special units such as the sievert (Sv) and millisievert (mSv, one thousandth of a sievert). Radiation-induced harm is controlled via enforcing exposure limits expressed as effective dose. Expected cancer cases can be easily computed based on the summed effective dose (person-sievert) for an irradiated group or population. Yet the current system of radiation protection needs revision because radiation-induced natural protection (hormesis) has been neglected. A novel, nonlinear, hormetic relative risk model for radiation-induced cancers is discussed in the context of establishing new radiation exposure limits for nuclear workers and the public.

THE VALIDATION OF COMPREHENSIVE SOFTWARE FOR THE ASSESSMENT OF RADIOLOGICAL IMPACTS ON HUMANS THROUGH BENCHMARK ANALYSIS WITH RADIOLOGICAL CODES

2020 ◽  
Vol 190 (3) ◽  
pp. 250-268
Author(s):  
Ali Haghighi Shad ◽  
Mitra Athari Allaf ◽  
Darioush Masti ◽  
Kamran Sepanloo ◽  
Seyed Amir Hossein Feghhi
Keyword(s):  
Thyroid Gland ◽  
Effective Dose ◽  
Nuclear Power ◽  
Power Plants ◽  
Whole Body ◽  
The Public ◽  
Loss Of Coolant Accident ◽  
Initial Stage ◽  
Loss Of Coolant ◽  
Accident Conditions

Abstract In this paper, a novel domestic code called KIANA was developed for the assessment of radiological impacts on the population in normal and accident conditions including design basis accident (DBA) and beyond DBA (BDBA) for the nuclear power plants. The validation process of the KIANA code was performed using the results of the DOZA_M radiological code, whose results are presented in the Final Safety Analysis Report (FSAR) of the Bushehr Nuclear Power Plant Unit One (BNPP-1). The calculations of KIANA are performed based on the Gaussian diffusion model. The developed KIANA code has the potential of calculating the concentration and radionuclide doses due to the pathways such as airborne, foodstuff, marine (both one and two boxes models), soils, animals, vegetation (with and without tritium) and other pathways without any restriction. In the current research, the individual dose from a cloud to the member of the public in the region of BNPP-1 in normal condition was calculated. Moreover, the total effective dose to the member of the public from the primary to the secondary leakage inside steam generators, large break loss-of-coolant accident (LBLOCA) and small break loss-of-coolant accident was calculated. Thyroid gland equivalent dose for the infant (1–8 years) in the case of LBLOCA at the BNPP in DBA conditions was also evaluated. Finally, the prevented dose at the initial stage for the whole body of adults after BDBA, prevented dose at the initial stage for the thyroid gland of children after BDBA and the effective dose during the first year after the accident (external body irradiation from presence in the area) in the case of BDBA are assessed. The KIANA simulation results showed a good agreement with the FSAR data of BNPP.

Internal effective dose assessment for the public based on the environmental radioactivity data in Portugal

2020 ◽  
Vol 168 ◽  
pp. 108558 ◽  
Author(s):  
M.J. Madruga ◽  
A.R. Gomes ◽  
J. Abrantes ◽  
M. Santos ◽  
E. Andrade ◽  
...  
Keyword(s):  
Effective Dose ◽  
Environmental Radioactivity ◽  
Dose Assessment ◽  
The Public
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