1 1 jour E 5 hours D 45 m 1 hour C 15 m B A 6m/s 3 …S. Mazidi 1, Bitam 1, B. Meftah 2, T, H....
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International Experts’ Meeting on Assessment and Prognosis in Response to a Nuclear or Radiological Emergency 20–24 April 2015, Vienna, Austria Development of a platform for the evaluation of the source term and the atmospheric dispersion of a nuclear facility in a radiological emergency event S. Mazidi 1 , Bitam 1 , B. Meftah 2 , T, H. Fellouh 2 1 Centre de Recherche Nucléaire de Draria, BP43 Sebala-Draria, Algiers-Algeria 2 COMmissariat à l’ENergie Atomique, 2Bld. Frantz Fanon, Alger Gare, Algiers-Algeria REPAS ATHNA.SYS Rad. Inventory Atmo. Dispersion SOURCE TERM RELEASE GIS / DISPLAY RADIOLOGICAL EMERGENCY Incident Accident SAFETY AUTHORITIES ORIGEN PLATFORM Kernel Facility data ATHNA.SYS (Neutronic & T/H Reactor Parameters) Hotspot SURFER GIS/GOOGLE EARTH Display Radioactive inventory calculation Calculation of the quantities of radioactive material released (Total and per fuel element) Axial dose distribution plot around the facility (partial and total doses) Charting the time evolution of the radioactive material released to the atmosphere 2D and 3D dose contours Display of dose contours of the contaminated area on satellite picture. Meteorological data As part of the implementation of the national emergency preparedness and intervention in nuclear accidents, the Algerian Commission of Atomic Energy (COMENA) is developing a Radiological Emergency Preparedness Advisory System (REPAS). The system would be used to monitor the operation of its nuclear facilities and to analyze abnormal events to continuously improve the safety systems and to develop and implement various emergency crisis plans. To take rapid and efficient corrective measures, decision makers require a swift estimate of the radiological conditions around the facility. To this end, specific tools are needed to evaluate the source term and the dispersion of radioactive products released in the environment to estimate the impact on the public and the environment in terms of radioactive exposures and radioactive deposits. A PC-based platform for the simulation and analysis of nuclear accidents in MTR type research reactors was developed. The platform allows a rapid determination of the radioactive source term and the atmospheric dispersion of radioactive products around the facility in the event of a reactor accident, taking into account pertinent parameters such as: reactor operating parameters, containment characteristics, meteorological parameters, etc… Thermal Canal Tangential Canal Radial Canal Neutron Radiography Core Biological Shield Thermal Column Fuel Elements Interim Storage Radial Canal SANS Neutron Reflectometer Reactor Pool The platform combines neutronic and thermal hydraulic calculations, using the ATHNA.Sys Analyser system, radioactive inventory estimation by the ORIGEN code and environment radioactive releases dispersion calculations by HOTSPOT code. GIS/Google Earth and SURFER10 are used to determine the geographical positions. Sample results of accident scenarios simulated for the case of the NUR research reactor according to the characteristic parameters of the facility and meteorological conditions specified in the table Fuel quantity (g) Fuel enrichment (% U235) leakage rate from the confinement (m 3 /s) free surface area (m 2 )/confinemen t volume (m 3 ) Filter retention factor Wind speed (m/s) Stability Plume Height (m) 22500 20 10 S=105 V=1062 0.5 v=3 F 15 Variation of reactor operation history Element Released quantity (Ci) Element Released quantity (Ci) Kr 83M 242.7 I133 1526.4 Kr 85M 573.5 I134 1708.1 Kr 85 1.6 I135 1419.8 Kr 87 1151.5 Ba140 27.7 Kr 88 1635.7 Sr 89 14.0 Kr 89 1728.1 Sr 90 0.1 Xe131M 14.1 Te127 35.3 Xe133 3053.1 Te127M 1.9 Xe135M 494.8 Te129 153.4 Xe135 1772.2 Te129M 18.7 Xe137 2320.7 Te132 974.6 Xe138 2706.3 Cs137 6.6 BR 82 0.1 Cs138 1494.9 I131 656.6 Rh105 4.8 I132 975.2 Ru103 10.6 0.1 1 5 10 0.01 0.1 1 Dose(rem) Position (km) A B C D E F 0.1 1 10 1E-3 0.01 0.1 1 Dose(rem) Distance (km) 15 m 30 m 45 m 0.1 1 10 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 Dose (rem) 1 hour 5 hours 1 jour Distance (Km) Variation of atmospheric conditions Change in reactor stack height Fission product ejection time Containment performance capacity Main Graphical Interfaces Wind speed 0.1 1 10 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 Dose (rem) Distance (Km) 3 m/s 6m/s 10 m/s
Transcript of 1 1 jour E 5 hours D 45 m 1 hour C 15 m B A 6m/s 3 …S. Mazidi 1, Bitam 1, B. Meftah 2, T, H....
International Experts’ Meeting on Assessment and Prognosis in Response to a Nuclear or Radiological Emergency
20–24 April 2015, Vienna, Austria
Development of a platform for the evaluation of the source term and the atmospheric dispersion of a nuclear facility in a radiological emergency event
S. Mazidi 1, Bitam 1, B. Meftah 2, T, H. Fellouh 2 1Centre de Recherche Nucléaire de Draria, BP43 Sebala-Draria, Algiers-Algeria
2COMmissariat à l’ENergie Atomique, 2Bld. Frantz Fanon, Alger Gare, Algiers-Algeria
REPAS
ATHNA.SYS
Rad. Inventory Atmo. Dispersion
SOURCE TERM
RELEASE
GIS / DISPLAY
RADIOLOGICAL EMERGENCY Incident Accident
SAFETY AUTHORITIES
ORIGEN
PLATFORM Kernel
Facility data ATHNA.SYS (Neutronic & T/H Reactor Parameters)
Hotspot SURFER
GIS/GOOGLE EARTH
Display
Radioactive inventory calculation Calculation of the quantities of
radioactive material released (Total and per fuel element)
Axial dose distribution plot around the facility (partial and total doses)
Charting the time evolution of the radioactive material released to the atmosphere
2D and 3D dose contours Display of dose contours of the
contaminated area on satellite picture.
Meteorological data
As part of the implementation of the national emergency preparedness and intervention in nuclear accidents, the Algerian Commission of Atomic Energy (COMENA) is developing a Radiological Emergency Preparedness Advisory System (REPAS). The system would be used to monitor the operation of its nuclear facilities and to analyze abnormal events to continuously improve the safety systems and to develop and implement various emergency crisis plans. To take rapid and efficient corrective measures, decision makers require a swift estimate of the radiological conditions around the facility. To this end, specific tools are needed to evaluate the source term and the dispersion of radioactive products released in the environment to estimate the impact on the public and the environment in terms of radioactive exposures and radioactive deposits.
A PC-based platform for the simulation and analysis of nuclear accidents in MTR type research reactors was developed. The platform allows a rapid determination of the radioactive source term and the atmospheric dispersion of radioactive products around the facility in the event of a reactor accident, taking into account pertinent parameters such as: reactor operating parameters, containment characteristics, meteorological parameters, etc…
Thermal Canal
Tangential Canal
Radial Canal
Neutron
Radiography
Core
Biological
Shield
Thermal Column
Fuel Elements
Interim Storage
Radial Canal
SANS
Neutron
Reflectometer
Reactor Pool
The platform combines neutronic and thermal hydraulic calculations, using the ATHNA.Sys Analyser system, radioactive inventory estimation by the ORIGEN code and environment radioactive releases dispersion calculations by HOTSPOT code. GIS/Google Earth and SURFER10 are used to determine the geographical positions.
Sample results of accident scenarios simulated for the case of the NUR
research reactor according to the characteristic parameters of the facility and meteorological conditions specified in the table
Fuel quantity
(g)
Fuel
enrichment
(% U235)
leakage rate
from the
confinement
(m3/s)
free surface area
(m2)/confinemen
t volume (m3)
Filter
retention
factor
Wind speed
(m/s)
Stability
Plume Height
(m)
22500 20 10 S=105
V=1062 0.5
v=3
F 15
Variation of reactor operation history
Element Released quantity (Ci) Element Released quantity (Ci)
Kr 83M 242.7 I133 1526.4
Kr 85M 573.5 I134 1708.1
Kr 85 1.6 I135 1419.8
Kr 87 1151.5 Ba140 27.7
Kr 88 1635.7 Sr 89 14.0
Kr 89 1728.1 Sr 90 0.1
Xe131M 14.1 Te127 35.3
Xe133 3053.1 Te127M 1.9
Xe135M 494.8 Te129 153.4
Xe135 1772.2 Te129M 18.7
Xe137 2320.7 Te132 974.6
Xe138 2706.3 Cs137 6.6
BR 82 0.1 Cs138 1494.9
I131 656.6 Rh105 4.8
I132 975.2 Ru103 10.6
0.1 1 5 10
0.01
0.1
1
Dos
e(re
m)
Position (km)
A
B
C
D
E
F
0.1 1 10
1E-3
0.01
0.1
1
Dos
e(re
m)
Distance (km)
15 m
30 m
45 m
0.1 1 10
0.1
0.2
0.3
0.4
0.5
0.6
0.7
0.8
0.9
1.0
Dos
e (re
m)
1 hour
5 hours
1 jour
Distance (Km)
Variation of atmospheric conditions Change in reactor stack height Fission product ejection time
Containment performance capacity
Main Graphical Interfaces
Wind speed
0.1 1 10
0.1
0.2
0.3
0.4
0.5
0.6
0.7
0.8
0.9
1.0
Dos
e (r
em)
Distance (Km)
3 m/s
6m/s
10 m/s
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