Simulation of the Atmospheric Dispersion of Radionuclides Using Gaussian Plume Model

2013 ◽  
Author(s):  
Ye Yang ◽  
Bo Cao ◽  
Yixue Chen
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Atmospheric Dispersion ◽  
Nuclear Accident ◽  
Radioactive Material ◽  
Gaussian Plume Model ◽  
Transport And Transformation ◽  
Plume Model ◽  
Gaussian Plume

The Chernobyl accident and Fukushima 1 Nuclear Power Plant accident are the most serious accidents in the history of the nuclear technology and industry. A large amount of radioactive materials from nuclear power plant were released, leading to huge damage and long-term effect on the environment as well as the human health neighbor to the plant. Therefore, simulating the transport and transformation of radionuclides in the atmosphere is significant for decision makers to take steps at all level. Now, many different dispersion models are widely applied and used to simulate the transport and transformation of radionuclide such as Gaussian model, Lagrangian model and Eulerian model. Though the Eulerian or Lagrangian models have several advantages, such as high spatial resolution, fully 3D descriptions of the meteorological, the simple Gaussian plume model is still widely chosen because of its higher accuracy and faster calculation. In this study, the atmospheric dispersion of leaked radioactive material during nuclear accident is simulated by using Gaussian plume model. The relative concentration distribution of the radionuclides and the trajectory of the distribution centrode are obtained in taking account of different geographical environments, wind direction, wind velocity, and stability category. These results can provide a favorable evidence for the management of nuclear accident emergency.

Variance of Atmosphere Dispersion Factor for Accident Release from Nuclear Power Plant

2012 ◽  
Vol 518-523 ◽  
pp. 1242-1246 ◽  
Author(s):  
Rui Ping Guo ◽  
Chun Lin Yang
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Probability Distribution ◽  
Wind Direction ◽  
Nuclear Power ◽  
Power Plants ◽  
Atmospheric Dispersion ◽  
Radioactive Material ◽  
The Difference ◽  
Release Height

The growing concern over the effect of atmosphere dispersion resulted from radioactive material was noticeable. This paper demonstrated the variance of atmosphere dispersion factor for accident release from nuclear power plant through running PAVAN (Atmospheric Dispersion of Radioactive Releases from Nuclear Power Plants) model. Also, we investigated the effect of release height (short for H) on atmosphere dispersion factor and compared the correlation between atmosphere dispersion factor and dispersion distance. Our results showed that atmosphere dispersion factor would descend with increased release height. As dispersion distance increasing, the tendency of atmosphere dispersion factor expressed complicated status caused by the difference of wind direction. It was illustrated that the phenomena was caused by the integrated action between the wind direction and release height. The probability distribution of atmosphere dispersion factor also validated that the distribution was depend on the wind direction. Probability analysis indicated that the atmosphere dispersion factor under H=100m was overall less than that under H=75m.

scholarly journals Development of radionuclide dispersion modeling software based on Gaussian Plume model

MATEMATIKA ◽  
2017 ◽  
Vol 33 (2) ◽  
pp. 149
Author(s):  
Shazmeen Daniar Shamsuddin ◽  
Nurlyana Omar ◽  
Meng Hock Koh
Keyword(s):  
Nuclear Power ◽  
Meteorological Data ◽  
Atmospheric Dispersion ◽  
Dispersion Modeling ◽  
Gaussian Plume Model ◽  
Plume Model ◽  
The North ◽  
Radioactive Effluent ◽  
Modeling Software ◽  
Gaussian Plume

It has come to attention that Malaysia have been aiming to build its own nuclear power plant (NPP) for electricity generation in 2030 to diversify the national energy supply and resources. As part of the regulation to build a NPP, environmental risk assessment analysis which includes the atmospheric dispersion assessment has to be performed as required by the Malaysian Atomic Energy Licensing Board (AELB) prior to the commissioning process. The assessment is to investigate the dispersion of radioactive effluent from the NPP in the event of nuclear accident. This article will focus on current development of locally developed atmospheric dispersion modeling code based on Gaussian Plume model. The code is written in Fortran computer language and has been benchmarked to a readily available HotSpot software. The radionuclide release rate entering the Gaussian equation is approximated to the value found in the Fukushima NPP accident in 2011. Meteorological data of Mersing District, Johor of year 2013 is utilized for the calculations. The results show that the dispersion of radionuclide effluent can potentially affect areas around Johor Bahru district, Singapore and some parts of Riau when the wind direction blows from the North-northeast direction. The results from our code was found to be in good agreement with the one obtained from HotSpot, with less than 1% discrepancy between the two.

scholarly journals An inverse modeling method to assess the source term of the Fukushima nuclear power plant accident using gamma dose rate observations

2013 ◽  
Vol 13 (6) ◽  
pp. 15567-15614 ◽  
Author(s):  
O. Saunier ◽  
A. Mathieu ◽  
D. Didier ◽  
M. Tombette ◽  
D. Quélo ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Dose Rate ◽  
Inverse Modeling ◽  
Nuclear Power ◽  
Source Term ◽  
Noble Gases ◽  
Atmospheric Dispersion ◽  
Nuclear Accident ◽  
Dose Rates

Abstract. The Chernobyl nuclear accident and more recently the Fukushima accident highlighted that the largest source of error on consequences assessment is the source term including the time evolution of the release rate and its distribution between radioisotopes. Inverse modeling methods, which combine environmental measurements and atmospheric dispersion models, have proven efficient in assessing source term due to an accidental situation (Gudiksen, 1989; Krysta and Bocquet, 2007; Stohl et al., 2012a; Winiarek et al., 2012). Most existing approaches are designed to use air sampling measurements (Winiarek et al., 2012) and some of them also use deposition measurements (Stohl et al., 2012a; Winiarek et al., 2013) but none of them uses dose rate measurements. However, it is the most widespread measurement system, and in the event of a nuclear accident, these data constitute the main source of measurements of the plume and radioactive fallout during releases. This paper proposes a method to use dose rate measurements as part of an inverse modeling approach to assess source terms. The method is proven efficient and reliable when applied to the accident at the Fukushima Daiichi nuclear power plant (FD-NPP). The emissions for the eight main isotopes 133Xe, 134Cs, 136Cs, 137Cs, 137mBa, 131I, 132I and 132Te have been assessed. Accordingly, 103 PBq of 131I, 35.5 PBq of 132I, 15.5 PBq of 137Cs and 12 100 PBq of noble gases were released. The events at FD-NPP (such as venting, explosions, etc.) known to have caused atmospheric releases are well identified in the retrieved source term. The estimated source term is validated by comparing simulations of atmospheric dispersion and deposition with environmental observations. The result is that the model-measurement agreement for all of the monitoring locations is correct for 80% of simulated dose rates that are within a factor of 2 of the observed values. Changes in dose rates over time have been overall properly reconstructed, especially in the most contaminated areas to the northwest and south of the FD-NPP. A comparison with observed atmospheric activity concentration and surface deposition shows that the emissions of caesiums and 131I are realistic but that 132I and 132Te are probably underestimated and noble gases are likely overestimated. Finally, an important outcome of this study is that the method proved to be perfectly suited to emergency management and could contribute to improve emergency response in the event of a nuclear accident.

scholarly journals An inverse modeling method to assess the source term of the Fukushima Nuclear Power Plant accident using gamma dose rate observations

2013 ◽  
Vol 13 (22) ◽  
pp. 11403-11421 ◽  
Author(s):  
O. Saunier ◽  
A. Mathieu ◽  
D. Didier ◽  
M. Tombette ◽  
D. Quélo ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Dose Rate ◽  
Inverse Modeling ◽  
Nuclear Power ◽  
Source Term ◽  
Atmospheric Dispersion ◽  
Nuclear Accident ◽  
Fukushima Accident ◽  
Dose Rates

Abstract. The Chernobyl nuclear accident, and more recently the Fukushima accident, highlighted that the largest source of error on consequences assessment is the source term, including the time evolution of the release rate and its distribution between radioisotopes. Inverse modeling methods, which combine environmental measurements and atmospheric dispersion models, have proven efficient in assessing source term due to an accidental situation (Gudiksen, 1989; Krysta and Bocquet, 2007; Stohl et al., 2012a; Winiarek et al., 2012). Most existing approaches are designed to use air sampling measurements (Winiarek et al., 2012) and some of them also use deposition measurements (Stohl et al., 2012a; Winiarek et al., 2014). Some studies have been performed to use dose rate measurements (Duranova et al., 1999; Astrup et al., 2004; Drews et al., 2004; Tsiouri et al., 2012) but none of the developed methods were carried out to assess the complex source term of a real accident situation like the Fukushima accident. However, dose rate measurements are generated by the most widespread measurement system, and in the event of a nuclear accident, these data constitute the main source of measurements of the plume and radioactive fallout during releases. This paper proposes a method to use dose rate measurements as part of an inverse modeling approach to assess source terms. The method is proven efficient and reliable when applied to the accident at the Fukushima Daiichi Nuclear Power Plant (FD-NPP). The emissions for the eight main isotopes 133Xe, 134Cs, 136Cs, 137Cs, 137mBa, 131I, 132I and 132Te have been assessed. Accordingly, 105.9 PBq of 131I, 35.8 PBq of 132I, 15.5 PBq of 137Cs and 12 134 PBq of noble gases were released. The events at FD-NPP (such as venting, explosions, etc.) known to have caused atmospheric releases are well identified in the retrieved source term. The estimated source term is validated by comparing simulations of atmospheric dispersion and deposition with environmental observations. In total, it was found that for 80% of the measurements, simulated and observed dose rates agreed within a factor of 2. Changes in dose rates over time have been overall properly reconstructed, especially in the most contaminated areas to the northwest and south of the FD-NPP. A comparison with observed atmospheric activity concentration and surface deposition shows that the emissions of caesiums and 131I are realistic but that 132I and 132Te are probably underestimated and noble gases are likely overestimated. Finally, an important outcome of this study is that the method proved to be perfectly suited to emergency management and could contribute to improve emergency response in the event of a nuclear accident.

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.

Atmospheric Dispersion and Deposition of Radionuclides from the Fukushima Daiichi Nuclear Power Plant Accident

Elements ◽  
2012 ◽  
Vol 8 (3) ◽  
pp. 195-200 ◽  
Author(s):  
A. Mathieu ◽  
I. Korsakissok ◽  
D. Quelo ◽  
J. Groell ◽  
M. Tombette ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Atmospheric Dispersion ◽  
Nuclear Power Plant Accident ◽  
Fukushima Daiichi
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