Jules Horowitz ReactorSviluppo dei primi dispositivi sperimentali JHRSviluppo dei primi dispositivi sperimentali JHR
The first test devices under developmentGilles Bignan; Christian GonnierCEA/Nuclear Energy DirectorateCEA/Nuclear Energy Directorate
contacts: [email protected];[email protected]
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JHR experimental capacities general characteristics
In reflectorUp to 5.5 1014 n/cm².s
20 fi d iti
In coreUp to 5.5 1014 n/cm².s > 1 MeVUp to 1015 n/cm² s > 0 1 MeV
~20 simultaneous experiments
~20 fixed positions (Φ100mm ; 1 position Φ200mm)
and 6 displacement systems
Up to 1015 n/cm².s > 0.1 MeV
7 Small locations (Φ~ 32 mm)3 Large locations (Φ~ 80 mm)
Fuel studies: up to 600 W/cm with a 1% 235U PWR rod
Fuel experiment(fast neutron flux – GEN IV)
g ( )
1% U PWR rodMaterial ageing(up to 16 dpa/y)
GEN II & III + GEN IV
Material ageing(low ageing rate)
Thermal neutron flux Fast neutron flux
Displacement systems:• Adjust the fissile power
Core Designed for UMo-Al fuel Start-up with U3Si2-Al fuel
70 MWth / 100 MWth
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Adjust the fissile power• Study transients
0 t / 00 t25 to 30 days cycle length
6-7 days shutdown
Milestones of a fuel development process in MTR
Qualification / Safety testsSelection / Characterization Q ySelection / Characterization
B h i d di Tests on industrial products10-15 years
Behavior understandingLaws and models set-up• Separate effect experiments
Tests on industrial products• Very high burn-ups• Soliciting LHGR time histories• Failed fuel rods
Fuel material knowledge• Input data for modeling• Microstructure selection
• Instrumented samples• On-line measurements• Adapted LHGR time histories
Failed fuel rods• Operation at the limits (ramps, lift-off,…)
• Accidental situations (RIA, LOCA,…)( , , )
Material studies Test of industrial « rodlet »
Numerous samples One single fuel rod
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Test devices are designed to fit with this development process
Material testing : overview of some phenomena
Material behaviour testing involves several parameters which can be interconnected. Experimentations focus on one or several parameters depending on the status in the material qualification process.material qualification process.(industrial material is a compromise between several parameters : corrosion / mechanical behaviour ; swelling / creeping ; …)
Parameters are :
-The behaviour under irradiation (evolution of the µstructure due to defects induced by fission products in the fuel, fission gas (and He) releases in the fissile matrix, defect induced in the cladding and structures by
FP (FG)(f t)high energy neutrons)-The temperature, the temperature gradient-The chemical interaction between materials (clad, fuel, fi i d t ) d b t fl id d t i l
fission
FP (FG)
FP (FG)
n (fast)
fission products,..) and between fluid and material(coolant / cladding) + chemical stability-The stresses (thermal stresses, pressure, fuel-clad mechanical interaction )
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mechanical interaction, ..)
R The experimental
JHR experimental capacities
Reactor capacities
The experimental hosting system capacities
(dedicated to an experimentation family)
Today : hosting systems are mainly dedicated to LWR applications
Sample holder and instrumentation(dedicated to an experiment)
Today : sample holders are
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Today : sample holders are « reference cases » for the hosting system design (choices of the project)
Hosting experimental systems under development
(M i l d di t d t LWR t di )CALIPSO & MICA
For material testing under high dpa and controlled thermal gradient OCCITANE
(Mainly dedicated to LWR studies)
(cladding and core internal structures) For pressure vessel steel testing
Four 2 Four 3
Four 1
Four 2 Four 3
Four 1
Four 4
Four 6
Four 5Four 4
Four 6
Four 5
MADISONADELINE
For fuel testing under
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For fuel testing under nominal conditions
off-normal conditions
MADISON EXPERIMENTAL HOSTING SYSTEMMultirod Adaptable Device for Irradiations of LWR fuel
Samples Operating in Normal conditions
Experimental cubicle
4 rod homogeneous irradiationunder PWR/BWR nominal conditions
p p g
Design and manufacturing in collaboration with IFE-Halden
Selection-Characterization and qualification (normal
Primary pumps, heat exchangers, high pressure pumps water chemistry module
Selection-Characterization and qualification (normal operation conditions) of fuel samples- Fuel behaviour (FGR, µstructure evolution, corrosion…)-Long-term irradiations -Re-irradiation before rampsS i t t (f l) d lifi tiReactor
pool Under water pipesTest device headTest device head
pressure pumps, water chemistry module, purification system, feed water tank, sampling system
-Screening test (fuel) or rod qualification
In pile test device
Heat exchangerHeat exchanger
Tight connectors
Fuel rod
Downcomer tubesTight connectors
Fuel rod
Downcomer tubes
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LVDTLVDT
ADELINE: Advanced Device for Experimenting up to Limits Irradiated Nuclear fuel Elements
Irradiation test device
Loop : thermal hydraulic
conditions and water treatment
Characterization and qualification of fuel samples (off-normal conditions)Power ramp tests ; Power to melt determination ; Rod over-pressure threshold (lift off)Fuel post failure behaviour ; Water contamination in case of clad failure
co d t o s a d wate t eat e t
LWR fuel rod testing beyond design criteria limits =>Designed for high power, transients,clad failure,…
p ;
Connected to FP lab (on-line FP sampling and measurement)
Purification systemFit up to alpha cell
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Fit up to alpha cell
Calispo: In Core Advanced Loop for Irradiation in Potassium SOdium
CALIPSO : Irradiation at controlled temperature, at low pressure, under high flux (under forced NaK convection)
Material irradiation (high ageing rate, 16dpa/y), in coreTemperature : 250 to 450°C; Δθ < 8°C (next step : 600°C)In core test device diameter: 33 mmIn core test device diameter: 33 mm
ne tion
zon
e
one
Impossibile v isualizzare l'immagine. La memoria del computer potrebbe essere insufficiente per aprire l'immagine oppure l'immagine potrebbe essere danneggiata. Riavviare il computer e aprire di nuovo il file. Se v iene visualizzata di nuovo la x rossa, potrebbe essere necessario eliminare l'immagine e inserirla di nuovo.
Within a fuel assembly of the core central region
Head
Electrical heaterElectrical heater
xcha
nger
zo
mpl
e ir
radi
at
Pum
p zo
ne
Hea
ting
zo
Core top lid
Head
EM Pump
flux
r flo
w
EM Pump
flux
r flo
w
Hea
t ex
Sam
Exp. Samples
Heat exchanger
Neu
tron
f
Wat
er
Exp. Samples
Heat exchanger
Neu
tron
f
Wat
er
MICA I di ti t t ll d t t
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g
NaK guide tube
g
NaK guide tube
MICA : Irradiation at controlled temperature, at low pressure, under medium flux (static NaK)
Exemple of LWR Material Testing
LWR C t t b di t t l i di ti i Mi / C liLWR : Creep tests ; bending tests ; sample irradiation in Mica / Calipso
LVDTLVDT
Creep test with a biaxial loading cell and biaxial online measuring
Pressurized rodlets (creep test under irradiation) LVDT
Traction bellows
Compression bellows
LVDT
Traction bellows
Compression bellows
system
S l i di ti ( i t t
Axial creep and
Zy-4 90mm claddingtube
Zy-4 90mm claddingtube
Sample irradiation (microstructure, swelling, tensile tests,..)
irradiation growth test
Diameter
gauge
Diameter
gauge
Bending test(stress relieving
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experiment)
Experimental device for Pressure Vessel steel qualification (Irma-Osiris => Occitane-JHR)
A gas capsule for improving safety margins and RPV lifetimeOut-of-Core Capsule for Irradiation Testing of Aging by NEutrons
- Knowledge of irradiated material behaviourtensile tests, resilience test (Charpy), crack
propagation tests …..i ith ill… comparison with surveillance programmes
- Warm Pre Stress Impact-Behaviour of Thermal affected zones- Effect of neutron spectrum on steel embrittlement
© D. Lidbury and T. Williams, FJOH 2010.
ect o eut o spect u o stee e b tt e e t
Main Characteristics (Irma) : ►Size of the experim. cavity : 60 x 25 x 500 mm ► temperature : 230°C to 300°C
(d i d f h ti ≤ 0 5 W/ )
Blocs Eléments chauffants
Blocs Eléments chauffants
(designed for gamma heating ≤ 0,5 W/g)► neutron flux : 3 – 5 1012 n/cm2/s (E ≥ 1 MeV) => 100mdpa/y
Four 2
Four 4 Four 5
Four 3
Four 1
Flux
Four 2
Four 4 Four 5
Four 3
Four 1
Flux
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AVANT
ARRIERE
Four 6
Porte‐échantillons
AVANT
ARRIERE
Four 6
Porte‐échantillons
High temp material irradiation (600 1000°C)
Hosting experimental systems under feasibility studies
LORELEI fuel testing under accidental conditions (LOCA)
High temp.material irradiation (600-1000°C)Large capacity MICA (material irrad) adapted to 1000°C gas
conditions (Phaeton type – Osiris technology)
(LOCA)pressu
eau
gaz
pressu
eau
gaz
pressu
eau
gaz
pressu
eau
gaz
T t ti
Vidange eau (retour eau pour trempe) + ligne pressu ? Injection gaz pour la vidange du dispositif Crayon combustible (Φ 9,6) Canal chaud (Φe 25) Zircone dense (Φe 29) Virole chauffante (Φe 33) Zircone poreuse (Φe 53)
Vidange eau (retour eau pour trempe) + ligne pressu ? Injection gaz pour la vidange du dispositif Crayon combustible (Φ 9,6) Canal chaud (Φe 25) Zircone dense (Φe 29) Virole chauffante (Φe 33) Zircone poreuse (Φe 53) Transmutation
studies
Canal froid (Φe 75 ) Ecran neutronique (Φe 55) Tube (s) dispo (1 ou 2 tubes) Creuset en zircone dense Niveau eau résiduelle Chaufferette
Canal froid (Φe 75 ) Ecran neutronique (Φe 55) Tube (s) dispo (1 ou 2 tubes) Creuset en zircone dense Niveau eau résiduelle Chaufferette
Corrosion loop for Zr alloy
corrosion and IASCCCALIPSO d t d t corrosion and IASCCCALIPSO adapted to
SFR fuel and materialNormal=> in core LWR : Adeline « FP » ; Adeline “power to melt” ; severe accident studies
GFR : fuel irradiation (normal and off-normal conditions)
Other topics
Neu
tron
flux
Wat
er fl
ow
Neu
tron
flux
Wat
er fl
ow
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ff normal => in reflectorGFR : fuel irradiation (normal and off normal conditions)Fuel characterization : basic properties under irradiation (thermal diffusivity, thermal creep,..)NaK guide tubNaK guide tub
Non Destructive Examination Benches in JHR
N i i dInitial checks of the experimental loadingAdjustment of the experimental protocolFinal NDE tests after the irradiation phase
Top viewSide view
n
nozzle
NIS
Top viewSide view
n
nozzle
NIS
Neutron imaging stand
Gamma and XR scanning system & multipurpose test Neutron source
Scanned object
Scanned object
DetectorNeutron source
Scanned object
Scanned object
DetectorCracks and gaps
benches in Hot cellsSample examinationMultipurpose stands :Aspect (visual macroscopy) Metrological
Hydrides lenses
Fuel or absorber composition
Neutron imaging stand in reactor pool
Aspect (visual, macroscopy), Metrological techniques (growing, creeping, density evolution…)Defaults characterisation (using US, X rays, eddy currents,...), Corrosion layer determination,..
X ray & stands
Test device examination
LINAC (X)
ShieldingDevicePool bank fixingPenetration
Bench
X-ray & γ stands
butio
n
X ray & stands
X-ray & γ stands
in reactor poolXR-detector
X-table
Y-table
Z-table
XR-collimator
VTT
con
trib
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X-ray & γ stands in storage pool
γ-detector
Tunable γ front collimator
Side cutawayView from the core
Conclusion
The first set of test devices is mainly dedicated to LWR (PWR including VVER ; BWR) : contin ation of the present e perimental capacit in OsirisBWR) : continuation of the present experimental capacity in Osiris
Beginning of detailed studies (before starting the manufacturing phase) :g g ( g g p )2011 (Madison) – 2012 (Adeline) - 2013 (Mica, Occitane)=> under operation 2016 - 2017
Studies are still under progress for safety analysis and flexibility under operation
Other test devices are under feasibility studies or conceptual design- to enlarge the experimental capacity for LWR g p p y(corrosion loop – IASCC ; LOCA)- to prepare the set of test devices dedicated to GEN IV
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