Irradiation Facilities Performance at RA-10

Irradiation Facilities Performance at RA-10

Irradiation Facilities Performance
at RA-10
Fernando Sánchez, Santiago Bazzana,
Ana Cintas, Nicolás Chiaraviglio,
Ariel Márquez, Juan Longhino,
Abelardo Yunes, Alexis Weir
Reactor and Radiation Physics Dept.
National Atomic Energy Commision
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RA-10 Presentation
• The RA-10 will be a 30 MW open pool reactor
for:
– radioisotope production,
– material testing and research,
– industrial applications.
• It will be constructed in Ezeiza, close to
Buenos Aires City.
• It is planned to be operative in 2018.
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RA-10 Designers
• The requirements and the concept were
stablished by CNEA in 2010.
• It is based mainly in OPAL reactor.
• INVAP is the main contractor.
• The engineering is divided between CNEA and
INVAP.
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Neutronic design resources
• Core design is developed by INVAP
• Facilities are developed by CNEA
• Codes:
– For core design: Cóndor-CITVAP mainly.
– For facilities design: MCNP5 and McStas
• Libraries:
– ENDF VI and VII mainly for MCNP
– WIMS-D4, WLUP, Helios for Cóndor
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Facilities
• Production:
– Radioisotopes: Mo-99, Ir-192, Lu-177, others
– Silicon NTD: 6’’, 8’’ y 10’’
• Material and nuclear fuel testing
– In core irradiadiation positions: fast and thermal.
– Loop for NPP fuels
• Science Research.
– Thermal and cold beams with neutron guides
– Pneumatic transfer system
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External facilities positions
COLD NEUTRON SOURCE
NEUTROGRAPHY
COLD BEAM
COLD BEAM
SILICON DOPING
SILICON DOPING
FUEL LOOP
MO-99
SILICON DOPING
SILICON DOPING
IR-192/LU-177
IR-192/LU-177
IR-192(I)/ORI
THERMAL BEAM
THERMAL BEAM
PNEUMATIC TUBES
SILICON DOPING
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MCNP Model
COLD NEUTRON SOURCE
COLD BEAM
COLD BEAM
SILICON DOPING
SILICON DOPING
FUEL LOOP
MO-99
SILICON DOPING
SILICON DOPING
IR-192/LU-177
IR-192/LU-177
IR-192(I)/ORI
THERMAL BEAM
THERMAL BEAM
PNEUMATIC TUBES
SILICON DOPING
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Molibdenum-99
Fission mini-plates
COOLANT FLOW
Irradiation
supporting
device
MCNP model
Set handled
by operator
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Iridium-192
COOLANT FLOW
“Pencil- type”
Ir container
MCNP model
Irradiation
supporting
device
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NPP fuel testing loop
Fuel pins
Coolant
Pressure envelope
Thermal isolation
MCNP model
Security tube
Ramp neutron absorber
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Silicon NTD
An homogeneus doping is required
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Neutron beam calculations
McStas
MCNP
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MCNP model of
Cold Neutron Source
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Pneumatics Transfer System
Pneumatic tubes
Capsule
MCNP model
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In-pool Neutron Radiography
Reflector tank
Beam extraction tube
Beam collimator
Flooding system
Sample box
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Production: Radioisotopes and Silicon
Purpose (no. of
positions)
Required
Calculated
Production
Mo-99 * ( x 10)
1-1.5 E14 n/cm2 s
1.5 E14 n/cm2 s
4000 Ci/week (a)
Ir-192 (med.) (x 4)
>1.8 E14 n/cm2 s
2.5 E14 n/cm2 s
34400 Ci/cycle
Lu-177
(x 4)
>1.8 E14 n/cm2 s
2.5 E14 n/cm2 s
1.85 Ci/mg cycle
Ir-192 (ind) (x 4)
1-1.5 E14 n/cm2 s
1 E14 n/cm2 s
12600 Ci/cycle
Other RI
1-1.5 E14 n/cm2 s
1 E14 n/cm2 s
-
1-4 E13 n/cm2 s
1.2 -2.3 n/cm2 s
80 ton/year
(x 4)
Silicon doping *
a) Without considering radiochemical process efficiency (about 60%)
*) Removable during operation.
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Materials and fuel testing
Purpose
Required
Calculated
Irradiation device under fast spectrum (x 2).
(e.g. Corrosion and hidruration studies)
>3E14 fast n/
cm2 s
5 E14 fast n/
cm2 s
Irradiation device under reactor spectrum (x 4):
(e.g. MTR plates, neutron damage, etc.)
1 E14 n/cm2 s
(integral)
3 E14 n/cm2 s
(integral)
NPP fuel LOOP
Steady state
Ramps
200-600 W
4-100 W/cm min
200-600 W
4-100 W/cm min
“fast”> 0.1 MeV
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Science Research
Purpose
Required
Computed
Pneumatic *
(NAA, other)
1-20 E13 n/cm2 s
2 < T/F < 500
1-20 E13 n/cm2 s
2 < T/F < 500
Thermal beam at Reactor Face
>1 E10 n/cm2 s
2.9 E10 n/cm2 s
Thermal beam at Guide Hall
>1 E9 n/cm2 s
2.5 E9 n/cm2 s
Cold beam at Reactor Face
> 4 E9 n/cm2 s
1.4 E10 n/cm2 s
Cold beam at Guide Hall
> 1 E9 n/cm2 s
5.4 E9 n/cm2 s
Cold Neutron Source
5 kW
5 kW (w/ 20% unc.)
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Thermal neutron flux
COLD NEUTRON SOURCE
COLD BEAM
COLD BEAM
SILICON DOPING
SILICON DOPING
FUEL LOOP
MO-99
SILICON DOPING
SILICON DOPING
IR-192/LU-177
IR-192/LU-177
IR-192(I)/ORI
THERMAL BEAM
THERMAL BEAM
PNEUMATIC TUBES
SILICON DOPING
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Conclusions
• All neutronic requirements are widely fulfilled.
• Developing of new technologies in Argentina:
–
–
–
–
Cold neutron source
Neutron guides calculations
Silicon NTD
Fuel-testing loop
• Strengthening of existing technologies:
–
–
–
–
Radioisotope production
Material and device testing
Neutron beams
Activation Analysis
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Thanks!
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