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: gilles.bignan@cea.fr;christian.gonnier@cea.fr

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