Jules Horowitz Reactor Il ruolo di JHR per lo sviluppo dei ... · Jules Horowitz Reactor Il ruolo...
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Jules Horowitz ReactorIl ruolo di JHR per lo sviluppo dei reattori di IV
GenerazioneTest devices under feasibility study – towards GEN IV
Gilles Bignan; Christian GonnierGilles Bignan; Christian GonnierCEA/Nuclear Energy Directorate
contacts: [email protected];[email protected]
ROMA seminar – November-10 th 2011 1
JHR experimental capacities general characteristics
Thermal neutron flux Fast neutron flux
In reflectorUp to 5 5 1014 n/cm² s
In coreUp to 5 5 1014 n/cm² s > 1 MeVUp to 5.5 10 n/cm .s
~20 fixed positions (Φ100mm ; 1 position Φ200mm)
and 6 displacement systems
Up to 5.5 10 n/cm .s > 1 MeVUp to 1015 n/cm².s > 0.1 MeV
7 Small locations (Φ~ 32 mm)
GEN IV Fuel studies: short term irradiation (off - Material ageing
3 Large locations (Φ~ 80 mm)
normal conditions ; Na)analytical irradiations
up to 16 dpa/y(High n flux - high γ
heating)Material ageing
Fuel experiment(fast neutron flux)
Long term irrad.; NaKN t filt (th l
Material ageing(low ageing rate)
Illustration 0.2
0.25
Position 103Position 101Position C313SFR core reference Neutron filters (thermal
flux)
GW
Existing fleet40-year plant life
Plant life extension beyond 40 years
Generation 4
Existing technologies PWR, BWR, …
of nuclear power evolution in France
0.05
0.1
0.15
1/Le
thar
gy
SFR core reference
ROMA seminar – November-10 th 2011 2
Generation 3
1980 1990 2000 2010 2020 2030 2040 2050 2060
Generation 3
1980 1990 2000 2010 2020 2030 2040 2050 2060
01.0E-09 1.0E-07 1.0E-05 1.0E-03 1.0E-01 1.0E+01
E [MeV]
First exemple : clad material evolution from GEN 3 to GEN 4
Gas cooled reactor (Gen 4)Cladding material : SiC or refractory metal Operating conditions :
Temp.: 1000/1200°CHelium 7MPa
Stresses (fuel clad interact.)Irradiation (fast neutron flux => high ageing rate )
Sodium cooled reactor (Gen 4)cladding material : stainless steel
Operating conditions :Temperature 400 / 550°C
Sodium
g g g )
Stresses (fuel clad mechanical interaction ; fuel swelling)Irradiation (fast neutron flux => high ageing rate 130 dpa
to 200 dpa with ODS ?)Clad Inner side Corrosion (FP)
Light Water reactor ; cladding material : Zr alloys
O ti diti
( )
Operating conditions : Temperature 300 / 320 °CWater + additives (corrosion : oxydation and hydriding)Stresses (water pressure 15MPa , fuel clad mechanical interaction)I di ti
ROMA seminar – November-10 th 2011 3
Irradiation
Gen 2 and 3 : mastered technology – very accurate experimentation
Second exemple : The fuel
Present fuel (UO2 ; UPuO2) :
Various µstructures (UO2, MOX) and evolutions (additives, grain size,…)
µstructure evolution due to irradiation (fg release, rim, …)Restructuration à fort taux (RIM)
Précipitation gaz de fissionf ( )
Needs : knowledge about fg release under normal and off-normal conditions, mitigate PCMI impact during power transients, knowledge about fuel behaviour under accidental conditions…
Fuel evolutions :
new materials : (UO2-MOX), U Pu C or U Pu N,
ROMA seminar – November-10 th 2011 4
minor actinides
new fuel concepts ; new µstructures
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 adapted to corrosion and IASCCCALIPSO adapted to
SFR fuel and materialNormal=> in core N
eutr
on fl
ux
Wat
er fl
ow
Neu
tron
flux
Wat
er fl
ow
LWR : Adeline « FP » ; Adeline “power to melt” ; severe accident studiesGFR : fuel irradiation (normal and off-normal conditions)
Other topics
ROMA seminar – November-10 th 2011 5
Off normal => in reflectorNaK guide tubNaK guide tub
GFR : fuel irradiation (normal and off normal conditions)Fuel characterization : basic properties under irradiation (thermal diffusivity, thermal creep,..)
JHR capabilities to investigate phenomena connected to the transmutation (Th Stummer PhD)
Test device concept = Diamino test device (Osiris)
For example : simulation of the fuel 2,50E-01
damaging phenomena (He release, irradiation and FP impact) by adjusting U and Am contents (but with the same µstructure) in a sample irradiated in 1,50E-01
2,00E-01
lux/
Leth
argy
SFR coreJHR ReferenceSFR BlanketPHENIX ECRIX H
µ ) pthe JHR reflector
Expected Experimental He Content and HM Depletion at EOL
10 000%
5,00E-02
1,00E-01
Nor
mal
ised
F
7.000%
8.000%
9.000%
10.000%
Diamino 15% Am 200efpdDiamino 7 5% Am 400efpd
0,00E+001E-09 1E-07 0,00001 0,001 0,1 10
E [MeV]
4.000%
5.000%
6.000%
% o
f HM
dep
letio
n
Diamino 7.5% Am 400efpdSFR blanket 15% Am 1700efpdSFR blanket 15% Am 3600 efpdJHR 15% Am max flux 270efpdJHR 15% Am max flux 520efpdJHR 15% Am 10% enr 10% flux 270 efpdJHR 15% Am 10% enr 10% flux 520 efpdJHR 15% Am depl 33% flux 270efpdSFR reference
JHR baselineHe production to fission ratio vs time
0.012
0.014
0.016
0.018
loss
He to fission ratio for various samples.
1.000%
2.000%
3.000%JHR 15% Am depl 33% flux 520efpdJHR 15% Am depl 10% flux 270efpdJHR 15% Am depl 10% flux 520efpd
expected DIAMINO results15% and 7.5% Am 0.002
0.004
0.006
0.008
0.01
He
mas
s/H
M m
ass SFR reference
JHR referenceJHR 20% enriched, 10% fluxJHR 2.5% Am, 33% fluxJHR 10% enriched, 33%flux
ROMA seminar – November-10 th 2011 6
0.000%0.00E+00 2.00E-01 4.00E-01 6.00E-01 8.00E-01 1.00E+00 1.20E+00 1.40E+00
mg He/g initial HM
0
018
036
054
072
090
010
8012
6014
4016
2018
0019
8021
6023
4025
2027
0028
8030
6032
4034
2036
0037
8039
6041
4043
2045
00
time [days]
CALIPSOevolutions toward broader applications
CALIPSO: Irradiation at controlled temperature, at low pressure, under high flux (under forced NaK convection)
Present design : Material irradiationIn core material irradiation, high ageing rate; T = 250 to 450°C (LWR)
Next step (1) : Material irradiation one
Next step (1) : Material irradiationIn core material irradiation, high ageing rate; ng
er z
one
rrad
iati
on z
o
zone
atin
g zo
ne
Core top lidg g g ;Temp.up to 650°C (liquid metal FR)
Next step (2) : Fuel irradiation
Hea
t ex
chan
Sam
ple
ir
Pum
p
He a
Electrical heaterElectrical heater
Fuel samples irradiation SFR conditions– In-core : long term irradiations (NaK-filters)– In-reflector : off-normal situations,
H Electrical heater
EM Pump
w
Electrical heater
EM Pump
w
power and flowrate transients (Na)
– Clad failure detection (gas sampling line ; FG release)
Fuel samples irradiation Pb Bi FR conditions
Exp. Samples
Heat exchanger
Neu
tron
flux
Wat
er fl
ow
Exp. Samples
Heat exchanger
Neu
tron
flux
Wat
er fl
ow
ROMA seminar – November-10 th 2011 7
Fuel samples irradiation Pb-Bi FR conditions g
NaK guide tube
g
NaK guide tube
Calipso : evolution for SFR material and fuel irradiation
Température NaK et gaineavec crayon 400 W/cm sans réchauffeur
700
Prelimirary calculation – SFR fuel applicationPresent design + capsule FUEL - Capsule
450
500
550
600
650
érat
ure
(°C)
Température de gaine
NaK montant
400W/cm
MATERIALS
600°C
Electrical heater
EM Pump
Electrical heater
EM Pump
Température NaK
700
800
Prelimirary calculation – SFR material applicationAdapted design (guide tube, flowrate)
Température NaK
700
800
Prelimirary calculation – SFR material applicationAdapted design (guide tube, flowrate)
250
300
350
400
450
Tem
pé
NaK descendant
300°C
Exp. Samples
utro
n flu
x
Wat
er fl
ow
Exp. Samples
utro
n flu
x
Wat
er fl
ow
500
600
Tem
péra
ture
(°C
)
NaK descendantNaK montant
500
600
Tem
péra
ture
(°C
)
NaK descendantNaK montant
Température NaK et gaineavec crayon 400 W/cm réchauffeur 10 kW Prelimirary calculation – SFR fuel application
Adapted design (flowrate ; heater ; NaK guide tube)
200-1100 -600 -100 400 900 1400
Altitude (mm)
600°C
Heat exchanger
Neu
Heat exchanger
Neu
200
300
400
NaK montant
200
300
400
NaK montant
500
550
600
650
e (°
C)
NaK descendantNaK montantT surface gaine
400W/cm300°C
FUEL – « direct cladding cooling »
600°C
NaK guide tubeNaK guide tube200
-1100 -600 -100 400 900 1400
Altitude (mm)
200-1100 -600 -100 400 900 1400
Altitude (mm)
350
400
450
500
Tem
péra
ture
300°C
ROMA seminar – November-10 th 2011 8
300-1100 -600 -100 400 900 1400
Altitude (mm)
300°C
0 25Calipso
0.2
0.25
Position 103Position 101Position C313SFR core reference
Evolution for SFR fuel irradiation
Neutron screens
SFRavec écran
SFRavec écran
0.1
0.15
1/Le
thar
gy
Sans écranSans écran 0
0.05
1.0E-09 1.0E-07 1.0E-05 1.0E-03 1.0E-01 1.0E+01
Sans écranSans écran 2.00E-01
2.50E-01
Position 103Position 101Position C313SFR core reference
E [MeV]
SFR
avec écran
SFR
avec écran
1.00E-01
1.50E-01
1/Le
thar
gyHf + Cd screens
SFRSFR
0.00E+00
5.00E-02
ROMA seminar – November-10 th 2011 9
0.00E 001.0E-09 1.0E-07 1.0E-05 1.0E-03 1.0E-01 1.0E+01
E [MeV]
High Temperature, instrumented, material Irradiation
Test device : Phaeton type - Osiris technology (Chouca-He )Example : Tests on SiC fibers performed in Osiris reactor at ~1000°C (Cedric – Crocus experiments)
~ + 600 mm / MP
~ + 900 mm / MP
~ + 600 mm / MP
~ + 900 mm / MPminicomposite
In-core zone
LVDT sensors
Out-of-core zone
Pneumatic loading unit
~ + 100 mm /MPIn-core zone
LVDT sensors
Out-of-core zone
Pneumatic loading unit
~ + 100 mm /MP
Movable jaw
Fixed jawMovable jaw
Fixed jaw
Core mid plane (MP)
~ -200 mm /MP
Core mid plane (MP)
~ -200 mm /MP
Dummy sample for temperature measurement Reference sample
Loaded sample
Dummy sample for temperature measurement Reference sample
Loaded sample
Samples
Thermocouples
Samples
Thermocouples
ROMA seminar – November-10 th 2011 10
High temperature material irradiation
Test device devoted to material testing at high ageing rate and high temperature (600-g g g p (1000°C , liquid metal FR & GFR ) use of a “gas loop technology” (helium natural convection or forced convection)Large capacity (numerous samples - 6x20) ; in-core large location
ROMA seminar – November-10 th 2011 11
Conclusion
The JHR design allows to investigate GENIV phenomenology (materials and fuels)
V li i l d i di i d fVery preliminary conceptual designs studies were carried out for SFR fuel and material irradiation (taking benefit of the “Calipso technology”)gy )These preliminary designs have to more deeply investigated
Neutron screens is still an issue
Adaptation to Pb-Bi technology has to be done
ROMA seminar – November-10 th 2011 12
GFR technology is an almost non-explored domain