scholarly journals Calculation of the Dose for Public Individuals Due to a Severe Accident at the Angra 2 Nuclear Plant, Brazil

2021 ◽  
Author(s):  
André Silva de Aguiar ◽  
Seung Min Lee ◽  
Gaianê Sabundjian
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Nuclear Plant ◽  
Emergency Planning ◽  
Severe Accident ◽  
Whole Body ◽  
The Public ◽  
Protective Actions ◽  
Radionuclide Release

Through a severe accident at nuclear power plant Angra 2, the whole body dose effective of the individuals members of the public located in the Emergency Planning Zones (EPZs) will be calculated, and later, the protective actions in these EPZs will be analyzed. Two different scenarios of radionuclide release into the atmosphere will be considered. In the first scenario, 2 h of the release of Xe, Cs, Ba, and Te, and the second scenario, 168 h of release.

Assessment of Internal Exposure Doses in Fukushima by a Whole Body Counter Within One Month after the Nuclear Power Plant Accident

2013 ◽  
Vol 179 (6) ◽  
pp. 663-668 ◽  
Author(s):  
Naoki Matsuda ◽  
Atsushi Kumagai ◽  
Akira Ohtsuru ◽  
Naoko Morita ◽  
Miwa Miura ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Internal Exposure ◽  
Whole Body ◽  
Nuclear Power Plant Accident ◽  
Body Counter ◽  
Whole Body Counter

Analysis of Inertization Strategies for the Filtered Containment Venting System in Cofrentes Nuclear Power Plant

2018 ◽  
Vol 4 (3) ◽  
Author(s):  
Kevin Fernández-Cosials ◽  
Gonzalo Jiménez ◽  
César Serrano ◽  
Luisa Ibáñez ◽  
Ángel Peinado
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Computational Model ◽  
Nuclear Power ◽  
Inert Atmosphere ◽  
Severe Accident ◽  
Nitrogen Injection

During a severe accident (SA) in a nuclear power plant (NPP), there are several challenges that need to be faced. To coup with a containment overpressure, the venting action will lower the pressure but it will release radioactivity to the environment. In order to reduce the radioactivity released, a filtered containment venting system (FCVS) can be used to retain iodine and aerosols radioactive releases coming from the containment atmosphere. However, during a SA, large quantities of hydrogen can also be generated. Hydrogen reacts violently with oxygen and its combustion could impair systems, components, or structures. For this reason, to protect the integrity of the FCVS against hydrogen explosions, an inertization system is found necessary. This system should create an inert atmosphere previous to any containment venting that impedes the contact of hydrogen and oxygen. In this paper, the inertization system for Cofrentes NPP is presented. It consists of a nitrogen injection located in three different points. A computational model of the FCVS as well as the inertization system has been created. The results show that if the nitrogen sweeps and the containment venting are properly synchronized, the hydrogen risk could be reduced to a minimum and therefore, the integrity of the FCVS would be preserved.

Nuclear Power Plant Emergency Preparedness: Results From an Evaluation of Michigan's Potassium Iodide Distribution Program

2012 ◽  
Vol 6 (3) ◽  
pp. 263-269 ◽  
Author(s):  
Laura R. Zwolinski ◽  
Martha Stanbury ◽  
Susan Manente
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Potassium Iodide ◽  
Emergency Preparedness ◽  
Nuclear Power ◽  
Power Plants ◽  
Body Part ◽  
Emergency Planning ◽  
Telephone Surveys ◽  
Fukushima Daiichi

ABSTRACTBackground: In 2009, the Michigan Department of Community Health (MDCH) made potassium iodide (KI), a nonprescription radio-protective drug, available by mailing vouchers redeemable at local pharmacies for KI tablets, at no cost to residents living within 10 miles of Michigan's 3 nuclear power plants (NPPs). MDCH conducted an evaluation of this program to determine Michigan's KI coverage and to assess general emergency preparedness among residents living near the NPPs.Methods: KI coverage was estimated based on redeemed voucher counts and the 2010 Census. Telephone surveys were administered to a random sample (N = 153) of residents living near Michigan's NPPs to evaluate general emergency preparedness, reasons for voucher use or nonuse, and KI knowledge.Results: Only 5.3% of eligible residences redeemed KI vouchers. Most surveyed residents (76.5%) were aware of living near an NPP, yet 42.5% reported doing “nothing” to plan for an emergency. Almost half of surveyed voucher users did not know when to take KI or which body part KI protects. Among voucher nonusers, 48.0% were either unaware of the program or did not remember receiving a voucher.Conclusions: Additional efforts are needed to ensure that all residents are aware of the availability of KI and that recipients of the drug understand when and why it should be taken. Minimal emergency planning among residents living near Michigan's NPPs emphasizes the need for increased emergency preparedness and awareness. Findings are particularly salient given the March 2011 Fukushima Daiichi Nuclear Power Plant emergency in Japan.(Disaster Med Public Health Preparedness. 2012;6:263–269)

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.

Onset of Gas Blowthrough During Melt Expulsion From a Hole in a RPV: Numerical Analysis Using the SIMMER Code

2006 ◽  
Author(s):  
Frank Kretzschmar
Keyword(s):  
Numerical Analysis ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Severe Accident ◽  
Core Material ◽  
Test Facility ◽  
Computer Codes ◽  
Direct Containment Heating ◽  
Heating Up

In the case of a severe accident in a nuclear power plant there is a residual risk, that the Reactor Pressure Vessel (RPV) does not withstand the thermal attack of the molten core material, of which the temperature can be about 3000 K. For the analysis of the processes governing melt dispersal and heating up of the containment atmosphere of a nuclear power plant in the case of such an event, it is important to know the time of the onset of gas blowthrough during the melt expulsion through the hole in the bottom of the RPV. In the test facility DISCO-C (Dispersion of Simulant Corium-Cold) at the FZK /6/, experiments were performed to furnish data for modeling Direct Containment Heating (DCH) processes in computer codes that will be used to extrapolate these results to the reactor case. DISCO-C models the RPV, the Reactor Coolant System (RCS), cavity and the annular subcompartments of a large European reactor in a scale 1:18. The liquid type, the initial liquid mass, the type of the driving gas and the size of the hole were varied in these experiments. We present results for the onset of the gas blowthrough that were reached by numerical analysis with the Multiphase-Code SIMMER. We compare the results with the experimental results from the DISCO-C experiments and with analytical correlations, given by other authors.

New Generation of Diamond Toolings for Facilitating Decommissioning Operations

2011 ◽  
Author(s):  
Claude Besson ◽  
Erico Mariotti ◽  
Alexandre Mouysset ◽  
Lorenz zur Nedden ◽  
Bernard Delannay
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Nuclear Plant ◽  
Diamond Tools ◽  
Nuclear Decommissioning ◽  
Specialized Equipment ◽  
New Generation

Diamond tools are well proven cutting, drilling and grinding technologies in many applications but need to be specifically optimized and adapted for the complex and varied structures of nuclear power plant in view of decontamination and decommissioning. The proper development and use of diamond tools in these extreme and complex conditions can only be achieved thanks to the combined talent of experienced nuclear plant contractors, engineers, technicians, operators of diamond tools, and the use of specialized equipment. This present paper is an overview of the possible applications of diamond tools in the different operations of Nuclear Decommissioning and Decontamination.

Design Concept of Composite Module for Nuclear Power Plant Construction

2004 ◽  
Author(s):  
Taihei Yotsuya ◽  
Kouichi Murayama ◽  
Jun Miura ◽  
Akira Nakajima ◽  
Junichi Kawahata
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Large Scale ◽  
Construction Method ◽  
Nuclear Plant ◽  
Small Scale ◽  
Modular Construction ◽  
Plant Construction ◽  
Composite Module

A composite module construction method is to be examined reflecting one of the elements of construction rationalization of a future nuclear plant planned by Hitachi. This concept is based on accomplishments and many successes achieved by Hitachi through application of the modular construction method to nuclear power plant construction over 20 years. The feature of the composite module typically includes a planned civil structure, such as a wall, a floor, and a post, representing modular components. In this way, an increased level of rationalization is expected in the conventional large-scale nuclear plants. Furthermore, the concept aiming at the modularization of all the building parts comprising medium- or small-scale reactors is also to be examined. Additional aims include improved reductions in the construction duration and rationalization through use of the composite module. On the other hand, present circumstances in nuclear plant construction are very pressing because of economic pressures. With this in mind, Hitachi is pursuing additional research into the introduction of drastic construction rationalization, such as the composite module. This concept is one of the keys to successful future plant construction, faced with such a severe situation.

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