Atmospheric dispersion modeling and radiological safety assessment for expected operation of Baiji nuclear power plant potential site

2019 ◽  
Vol 127 ◽  
pp. 156-164 ◽  
Author(s):  
Ismael Mohammed Mohammed Saeed ◽  
Muneer Aziz Mohammed Saleh ◽  
Suhairul Hashim ◽  
Ahmad Termizi bin Ramli ◽  
Shwan H.H. Al-Shatri
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Safety Assessment ◽  
Atmospheric Dispersion ◽  
Dispersion Modeling ◽  
Potential Site ◽  
Radiological Safety

Estimation of Radiological Consequences at a Proposed Nuclear Power Plant Site Using Atmospheric Dispersion Code

2020 ◽  
Vol 7 (1) ◽  
Author(s):  
Kwame Gyamfi ◽  
Sylvester Attakorah Birikorang ◽  
Emmanuel Ampomah-Amoako ◽  
John Justice Fletcher
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Atmospheric Dispersion ◽  
Atmospheric Stability ◽  
Assessment System ◽  
Severe Accident ◽  
Dispersion Modeling ◽  
Stability Class ◽  
Total Effective Dose Equivalent

Abstract Atmospheric dispersion modeling and radiation dose calculation have been performed for a generic 1000 MW water-water energy reactor (VVER-1000) assuming a hypothetical loss of coolant accident (LOCA). Atmospheric dispersion code, International Radiological Assessment System (InterRAS), was employed to estimate the radiological consequences of a severe accident at a proposed nuclear power plant (NPP) site. The total effective dose equivalent (TEDE) and the ground deposition were calculated for various atmospheric stability classes, A to F, with the site-specific averaged meteorological conditions. From the analysis, 3.7×10−1 Sv was estimated as the maximum TEDE corresponding to a downwind distance of 0.1 km within the dominating atmospheric stability class (class A) of the proposed site. The intervention distance for evacuation (50 mSv) and sheltering (10 mSv) were estimated for different stability classes at different distances. The intervention area for evacuation ended at 0.5 km and that for sheltering at 1.5 km. The results from the study show that designated area for public occupancy will not be affected since the estimated doses were below the annual regulatory limits of 1 mSv.

Assessment of the Contamination by 14C Airborne Releases in the Vicinity of the Ignalina Nuclear Power Plant

Radiocarbon ◽  
2019 ◽  
Vol 61 (5) ◽  
pp. 1185-1197 ◽  
Author(s):  
Algirdas Pabedinskas ◽  
Evaldas Maceika ◽  
Justina Šapolaitė ◽  
Žilvinas Ežerinskis ◽  
Laurynas Juodis ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Tree Ring ◽  
Tree Rings ◽  
Nuclear Power ◽  
Atmospheric Dispersion ◽  
Measurement Data ◽  
Analysis Data ◽  
Dispersion Modeling ◽  
Ring Analysis

ABSTRACTA radiocarbon (14C) activity analysis in the tree rings around Ignalina nuclear power plant (INPP) has been carried out with the aim to test the hypothesis to use 14C tree-ring analysis data as a tool for the reconstruction of gaseous releases from NPP to the environment. The INPP has been in decommissioning state since the end of 2009. Tree-ring samples for 14C analysis were collected 7 yr after final power unit shutdown from the INPP vicinity. The samples from 5 sampling locations were collected, prepared and measured using the Single Stage Accelerator Mass Spectrometer (SSAMS). Data analysis represents observable Ignalina NPP influence by 14C increase up to 15 pMC (percent modern carbon) in tree rings. Good correlations of the 14C concentrations and wind direction were obtained. The main purpose of this article was to match 14C measurement data along with the atmospheric dispersion modeling of emissions in order to retrospectively characterize the emission source.

scholarly journals Radiological safety assessment for incident-free transportation of radioactive decontamination waste after the Fukushima nuclear power plant accident

2019 ◽  
Vol 34 (2) ◽  
pp. 201-208
Author(s):  
Min Kim ◽  
Ji Song ◽  
Jin Park ◽  
Tae Do ◽  
Jin Lee ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Safety Assessment ◽  
Nuclear Power Plant Accident ◽  
The Public ◽  
Exposed Individual ◽  
Study Results ◽  
Radiological Safety ◽  
Effective Doses

Radioactive decontamination waste generated by remediation following the Fukushima nuclear power plant accident was recently transported from its temporary storage sites to interim storage facilities as a pilot test. A transportation plan for the radioactive decontamination waste will be developed based on this pilot transportation experience and radiological safety assessment of pilot transportation. The objective of this study was to assess radiation doses to the public and crew workers released during incident-free pilot transportation. External dose rates around a transportation vehicle were calculated by using the Monte Carlo N-Particle code. Collective doses and maximally exposed individual doses to the public and effective doses to crew workers were calculated by using INTERTRAN. Two transportation routes, Asakawa-machi to Okuma-machi and Iwaki-shi to Okuma-machi, were considered. The maximum radioactivity concentration in the decontamination waste was calculated to be 660 kBqkg?1 which meets the value laid down by the guidelines of Japan's Ministry of the Environment. The collective doses to the public per shipment were 1.9 10?3 person-mSv for the Asakawa route and 2.2 10?4 person-mSv for the Iwaki route. Maximally exposed individual doses to the public were 9.6 10?7 mSv for the Asakawa route and 2.7 10?5 mSv for the Iwaki route. The total effective doses to crew workers were 0.27 mSv for the Asakawa route assuming five shipments per worker and 1.07 mSv for the Iwaki route assuming 45 shipments per worker. The radiation dose levels to the public and workers evaluated in this study were much lower than the annual dose limits for the general public and radiation workers. These study results can be used to develop transportation plans and guidelines for decontamination waste transportation.

scholarly journals Assessment of potential human health and environmental impacts of a nuclear power plant (NPP) based on atmospheric dispersion modeling

Atmósfera ◽  
2015 ◽  
Vol 28 (1) ◽  
pp. 13-26 ◽  
Author(s):  
Abubakar Sadik Aliyu ◽  
◽  
Ahmad Termizi Ramli ◽  
Muneer Aziz Saleh ◽  
◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Human Health ◽  
Environmental Impacts ◽  
Nuclear Power ◽  
Atmospheric Dispersion ◽  
Dispersion Modeling ◽  
Potential Human Health

scholarly journals Radiological safety analysis of Rooppur Nuclear Power Plant site using atmospheric dispersion model

2020 ◽  
Vol 11 (3/4) ◽  
pp. 284
Author(s):  
Altab Hossain ◽  
Sarim Salman Karim ◽  
Maruf Hasan Khan ◽  
Faraji Samiul Haque Bijoy
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Dispersion Model ◽  
Atmospheric Dispersion ◽  
Safety Analysis ◽  
Plant Site ◽  
Radiological Safety ◽  
Atmospheric Dispersion Model

scholarly journals Radiological safety analysis of Rooppur Nuclear Power Plant site using atmospheric dispersion model

2020 ◽  
Vol 11 (3/4) ◽  
pp. 284
Author(s):  
Maruf Hasan Khan ◽  
Faraji Samiul Haque Bijoy ◽  
Altab Hossain ◽  
Sarim Salman Karim
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Dispersion Model ◽  
Atmospheric Dispersion ◽  
Safety Analysis ◽  
Plant Site ◽  
Radiological Safety ◽  
Atmospheric Dispersion Model

scholarly journals The radiological assessment, hazard evaluation, and spatial distribution for a hypothetical nuclear power plant accident at Baiji potential site

2020 ◽  
Vol 32 (1) ◽  
Author(s):  
Ismael Mohammed Mohammed Saeed ◽  
Muneer Aziz Mohammed Saleh ◽  
Suhairul Hashim ◽  
Younis Mohammed Salih Hama ◽  
Khaidzir Hamza ◽  
...  
Keyword(s):  
Spatial Distribution ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Hazard Evaluation ◽  
Radiological Assessment ◽  
Nuclear Power Plant Accident ◽  
Potential Site
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