Jules Horowitz Reactor Sviluppo dei primi dispositivi ...

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]

ROMA seminar – November 10 th 2011 1

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


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


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 )


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


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


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


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


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

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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


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


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


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


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


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


Jules Horowitz Reactor Sviluppo dei primi dispositivi ...

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