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Zentralabteilung Forschungsreaktoren
Contents
- The German FRJ-2 Research Reactor
- Operation and Decommissioning
- Distribution of Neutronflux and activity
Geometrical Nodalization (MCNP)
ORIGEN Model and Calculations
- Effects of geometrical inhomogenities
- Results and Summary
ANALYSIS OF THE ACTIVITY INVENTORY FOR THE DECOMISSIONING PLAN OF THE GERMAN FRJ-2 RESEARCH REACTOR
R. NABBI, P. BOURAUEL, G. DAMM
Type: Tank
Operation: 1962 - 2006
Thermal Power: 10/15/23 MW
Moderator / Coolant: D2O (Heavy Water)
Vertical experimental tubes: 25 inside core and 25 inside reflector
Horizontal experimental tubes: 10 inside D2O and 21 inside graphite reflector
Neutron flux:
core max.: 3,2*1014 1/(cm2s)
reflector max.: 2,6*1014 1/(cm2s)
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The main design data of the FRJ-2 Research Reactor
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Nab-April2007
MCNP: Arrangement of the beam tubes in the structures
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MCNP: FRJ-2 model with the nodalized reactor core
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MCNP: FRJ-2 model with the nodalized reactor core
3-d Distribution of the n-flux in the reactor core midplane and fuel element(MCNP-BURN)
Core center
Core Fuel element
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MCNP: Nodalization of the whole reactor block
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Visualization of the streaming effect
Cd-layer
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MCNP: Distribution of thermal N-flux
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Neutron flux distribution in the structures
Detailed neutron flux distribution in the structure
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Distribution of N-flux above the Cd-layer
Nab-April2007
Distribution of thermal N-flux in the steel tank
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Total activity in the structures of the reactor
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Nuclide activity in different structures after 5 years cooling time
Gesamtaktivität: 1,92E+14 Bq
Komponenten H3 C14 Fe55 Co60 Ni63 Zn65 Ag108m Ag110m Cd113m Ba133 Eu152 Eu154 Summe
Reaktor-Aluminiumtank
Tankhülle 9,84E+04 1,47E-09 2,26E+12 1,15E+12 1,74E+09 3,77E+10 0,00E+00 0,00E+00 0,00E+00 0,00E+00 0,00E+00 3,45E+12
Strahlrohre 1,25E+04 0,00E+00 1,28E+12 6,79E+11 1,01E+09 2,13E+10 0,00E+00 0,00E+00 0,00E+00 0,00E+00 0,00E+00 1,98E+12
Zu- und Rücklaufrohre 1,48E+03 0,00E+00 2,04E+11 1,09E+11 1,61E+08 3,40E+09 0,00E+00 0,00E+00 0,00E+00 0,00E+00 0,00E+00 3,17E+11
Gitterplatte 6,86E+04 8,33E-09 2,71E+11 1,22E+11 1,98E+08 4,54E+09 0,00E+00 0,00E+00 0,00E+00 0,00E+00 0,00E+00 3,98E+11
Summe 1,81E+05 9,80E-09 4,02E+12 2,06E+12 3,11E+09 6,70E+10 0,00E+00 0,00E+00 0,00E+00 0,00E+00 0,00E+00 0,00E+00 6,14E+12
Graphitreflektor
Graphit 9,48E+13 7,54E+10 1,56E+13 1,95E+11 5,44E+11 5,48E+08 0,00E+00 0,00E+00 0,00E+00 0,00E+00 0,00E+00 1,11E+14
Stahltank
Boral 6,11E+01 1,44E+05 0,00E+00 0,00E+00 0,00E+00 0,00E+00 0,00E+00 0,00E+00 0,00E+00 0,00E+00 0,00E+00 1,44E+05
Stahltank innen 1,24E+00 5,40E+05 4,07E+13 4,59E+12 4,17E+07 9,19E+09 0,00E+00 0,00E+00 0,00E+00 0,00E+00 0,00E+00 4,54E+13
Bleischild 0,00E+00 0,00E+00 0,00E+00 3,08E+07 2,29E+08 3,99E+03 1,19E+09 4,22E+09 0,00E+00 0,00E+00 0,00E+00 5,67E+09
Stahltank aussen 0,00E+00 6,37E+04 4,81E+12 5,42E+11 4,92E+06 1,08E+09 0,00E+00 0,00E+00 0,00E+00 0,00E+00 0,00E+00 5,35E+12
Summe 6,23E+01 7,48E+05 4,56E+13 5,13E+12 2,75E+08 1,03E+10 1,19E+09 4,22E+09 0,00E+00 0,00E+00 0,00E+00 0,00E+00 5,07E+13
Aluminiumtankstopfen
CrNi- Stahlplatte 0,00E+00 0,00E+00 4,86E+12 3,82E+12 1,06E+12 2,26E+07 0,00E+00 0,00E+00 0,00E+00 0,00E+00 0,00E+00 9,75E+12
Cadmiumbleche 0,00E+00 0,00E+00 2,04E+06 7,41E-01 0,00E+00 0,00E+00 0,00E+00 2,30E-13 3,81E+10 0,00E+00 0,00E+00 0,00E+00 3,81E+10
Bleischild 0,00E+00 0,00E+00 0,00E+00 1,19E+06 8,86E+06 1,16E+02 4,60E+07 1,64E+08 0,00E+00 0,00E+00 0,00E+00 2,20E+08
Stahlplatte 0,00E+00 2,86E+03 2,16E+11 2,43E+10 2,21E+05 4,87E+07 0,00E+00 0,00E+00 0,00E+00 0,00E+00 0,00E+00 2,40E+11
Schwerbeton Eisenschrot (ohne Bor) 3,22E+09 1,85E+04 7,63E+09 1,52E+07 0,00E+00 0,00E+00 0,00E+00 0,00E+00 0,00E+00 1,13E+08 1,11E+07 1,10E+10
Summe 3,22E+09 2,14E+04 5,08E+12 3,85E+12 1,06E+12 7,13E+07 4,60E+07 1,64E+08 3,81E+10 0,00E+00 1,13E+08 1,11E+07 1,00E+13
Thermische Säule
Graphit 4,82E+10 3,54E+07 7,35E+09 8,25E+07 2,60E+08 2,58E+05 0,00E+00 0,00E+00 0,00E+00 0,00E+00 0,00E+00 5,59E+10
Ringschild
Untere Stahlplatte 0,00E+00 1,68E+04 1,27E+12 1,43E+11 1,30E+06 2,86E+08 0,00E+00 0,00E+00 0,00E+00 0,00E+00 0,00E+00 1,41E+12
Cadmiumbleche 0,00E+00 0,00E+00 6,91E+05 3,17E-02 0,00E+00 0,00E+00 5,82E-04 1,75E+00 1,79E+10 0,00E+00 0,00E+00 0,00E+00 1,79E+10
Bleischild 0,00E+00 0,00E+00 0,00E+00 3,40E+03 2,52E+04 4,86E-04 1,31E+05 4,67E+05 0,00E+00 0,00E+00 0,00E+00 6,27E+05
Stahlplatte 0,00E+00 4,62E+00 3,49E+08 3,93E+07 3,57E+02 7,86E+04 0,00E+00 0,00E+00 0,00E+00 0,00E+00 0,00E+00 3,88E+08
Schwerbeton unteres Ringschild (ohne Bor)1,20E+08 6,91E+02 2,85E+08 5,69E+05 0,00E+00 0,00E+00 0,00E+00 0,00E+00 0,00E+00 4,22E+06 4,15E+05 4,10E+08
Schwerbeton oberes Ringschild (ohne Bor)3,57E+07 2,05E+02 8,46E+07 1,69E+05 0,00E+00 0,00E+00 0,00E+00 0,00E+00 0,00E+00 1,25E+06 1,23E+05 1,22E+08
Summe 1,56E+08 1,77E+04 1,27E+12 1,43E+11 1,33E+06 2,86E+08 1,31E+05 4,67E+05 1,79E+10 0,00E+00 5,48E+06 5,38E+05 1,43E+12
Biologischer Schild
Schwerbeton Eisenschrot (mit Bor) 8,10E+10 3,31E+05 1,93E+11 1,28E+10 0,00E+00 0,00E+00 0,00E+00 0,00E+00 0,00E+00 2,85E+09 2,80E+08 2,90E+11
Schwerbeton Baryt 1,51E+12 3,12E+07 3,67E+10 7,16E+09 0,00E+00 0,00E+00 0,00E+00 0,00E+00 5,31E+11 5,31E+10 5,22E+09 2,14E+12
Summe 1,59E+12 3,15E+07 2,30E+11 1,99E+10 0,00E+00 0,00E+00 0,00E+00 0,00E+00 0,00E+00 5,31E+11 5,60E+10 5,50E+09 2,43E+12
Summe insgesamt 9,65E+13 7,55E+10 7,18E+13 1,14E+13 1,61E+12 7,82E+10 1,23E+09 4,39E+09 5,60E+10 5,31E+11 5,61E+10 5,51E+09 1,82E+14
Tabelle 6: Aktivitäten der einzelnen Nuklide nach 5 Jahren nach der Abschaltung in Bq
Zentralabteilung Forschungsreaktoren
Distribution of the total activity in radial structures
1,0E+00
1,0E+02
1,0E+04
1,0E+06
1,0E+08
1,0E+10
1,0E+12
Sp
ezi
fis
ch
e A
kti
vit
ät
Bq
/kg
Tan
kh
ülle
Gra
ph
it
Bo
ral
Sta
hltan
k
Ble
isc
hild
Sta
hltan
k
Beto
n (F
e)
Bary
t
Nach 0,1 Jahren
Nach 5 Jahren
Zentralabteilung Forschungsreaktoren
Summary & Conclusions
A sophisticated MCNP model is generated on the basis of detailed material
composition and geometrical design data
Using the MCNP model the neutron flux was determined with a high level of
accuracy and low standard deviations
Using ORIGEN, the activity inventory in different components could be
determined. The calculations resulted in a detailed activity map allowing
The determination of the low and high level activity zones
Reduction of waste material mass and volume
Optimum dismantling process with minimum radiation effect
The main source of activity are H3, Fe55 and Co60 resulting from the activation
of impurities
Horizontal cut view of the whole reactor block
Th
erm
. P
ower
Central FE
