MICROSTRUCTURE EVOLUTION IN ION- IRRADIATED …(compression and/or stoichiometry variations) o...

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MICROSTRUCTURE EVOLUTION IN ION- IRRADIATED OXIDIZED ZIRCALOY-4 STUDIED WITH SYNCHROTRON RADIATION MICRO-DIFFRACTION AND TRANSMISSION ELECTRON MICROSCOPY ASTM 18 TH INTERNATIONAL SYMPOSIUM ON ZIRCONIUM IN THE NUCLEAR INDUSTRY, MAY 15-19 TH 2016, HILTON HEAD, SC, USA K.COLAS, R. VERLET, M. TUPIN, M. JUBLOT Département des Matériaux pour le Nucléaire, CEA Saclay, 91191 Gif sur Yvette Cedex, France. Z. CAI Advanced Photon Source, Argonne National Laboratory, 60439, Argonne, IL, United States of America. K. WOLSKI Centre SMS, Ecole des Mines de Saint Etienne, 42023 Saint Etienne Cedex, France.

Transcript of MICROSTRUCTURE EVOLUTION IN ION- IRRADIATED …(compression and/or stoichiometry variations) o...

Page 1: MICROSTRUCTURE EVOLUTION IN ION- IRRADIATED …(compression and/or stoichiometry variations) o Irradiation of the oxide releases some of the compressive stresses in the monoclinic

MICROSTRUCTURE EVOLUTION IN ION-

IRRADIATED OXIDIZED ZIRCALOY-4

STUDIED WITH SYNCHROTRON

RADIATION MICRO-DIFFRACTION AND

TRANSMISSION ELECTRON

MICROSCOPY

ASTM 18TH INTERNATIONAL SYMPOSIUM ON ZIRCONIUM IN THE

NUCLEAR INDUSTRY, MAY 15-19TH 2016, HILTON HEAD, SC, USA

K.COLAS, R. VERLET, M. TUPIN, M. JUBLOT

Département des Matériaux pour le Nucléaire, CEA Saclay, 91191

Gif sur Yvette Cedex, France.

Z. CAI

Advanced Photon Source, Argonne National Laboratory, 60439,

Argonne, IL, United States of America.

K. WOLSKI

Centre SMS, Ecole des Mines de Saint Etienne, 42023

Saint Etienne Cedex, France.

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BACKGROUND: STUDY OF IMPACT OF IRRADIATION

ON ZIRCONIUM CLADDING

PWR

Reactor

346°C

Loop

346°C

Autoclave

354°CAutoclave

346°C

Time (days)

Oxid

eth

ickn

ess

[Gilbon, Monographie DEN, 2008]

PWR environment,

including neutron

irradiation,

significantly

increases the

corrosion kinetics

of Zircaloy-4

cladding

Out-of-pile Zircaloy-4

corrosion kinetics

under isothermal

conditions

t(days)

Post-transition cycles

Pre-transition

Transition

Post-transition

X(µm)

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FACTORS IMPACTING CORROSION UNDER

IRRADIATION

Several hypotheses have been advanced to explain the in-reactor

acceleration of corrosion of Zircaloy-4

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Hydride accumulation at

the oxide/metal interfaceInfluence of SnIrradiation Effects

Metal irradiationOxide irradiation Radiolysis

[Bossis, ASTM, 2005] [Tupin, Corr. Sc., 2015][Garner, ANS LWR, 2007]

Effect of Li in water

Radiation damage Precipitate

AmorphizationIron dissolution

[Zu, Phil. Mag., 2012]

[Lefebvre,

JNM,

1990]

[Lefebvre,

JNM,

1989]

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MOTIVATION OF STUDY

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Irradiation effects have a strong impact on Zircaloy-4 corrosion.

It is important to separate the various effects of irradiation in order to understand

their impact on the corrosion mechanisms.

Impact of metal irradiation

o Objective: Study the impact of ion-irradiation induced damage of the metal matrix on

corrosion kinetics.

o What is the radiation damage induced by ion-irradiation of the metal matrix?

o How are the corrosion kinetics affected by metal matrix irradiation?

o What is the microstructure of the oxide layer formed on an irradiated matrix?

Impact of oxide irradiation

o Objective: Study the impact of ion-irradiation induced damage of the oxide layer on

corrosion kinetics.

o How is the oxide microstructure affected by ion-irradiation?

o How does oxide irradiation affect the corrosion kinetics?

o What is the microstructure of an oxide layer formed on an irradiated oxide layer?

How do metal irradiation and oxide irradiation compare in terms of oxide

microstructure and corrosion kinetics?

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EXPERIMENTAL PROCEDURES

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Irradiation experiments

JANNUS irradiation platform

Corrosion experiments

• Static 0.5 L autoclave

• 360°C, 187 bars

• PWR chemistry: 2 ppm

[Li], 1000 ppm [B]

Oxide irradiation

• 1.3 MeV He+

• 20°C irr. T°C

• Fluence: 1017 ions/cm²

• Avg Flux: 8.1012 ions/cm²/s

• Max. damage: 0.35 dpa JANNUS Saclay, France

Metal irradiation

• 300 keV H+

• 350°C irr. T°C

• Fluence: 1018 ions/cm²

• Avg Flux: 8.1013 ions/cm²/s

• Max. damage: 4.9 dpa

JANNUS Orsay, France

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EXPERIMENTAL TECHNIQUE: SYNCHROTRON

MICRO-DIFFRACTION AND FLUORESCENCE

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Fluorescence detector

X-ray beam

Epoxy

Oxide

Metal

CCD Camera

Fluorescence spectrum

Diffraction rings

Integration

XRD pattern of

one point3D Map of a line scan

[Yilmazbayhan, JNM, 2004]

Evolution across

oxide thickness of:

• Peak intensity:

tetragonal phase

fraction, texture

• Peak position:

oxide elastic strain,

stoichiometry

• Peak FWHM:

oxide grain size

Advanced Photon Source Synchrotron,

ANL, USA - 2-ID-D Beamline

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IMPACT OF METAL IRRADIATION ON

CORROSION BEHAVIOR

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ASTM 18th Int. Symp. on Zr. in the Nuc. Ind.,

May 15-19, 2016, Hilton Head, SC, USA

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IMPACT OF IRRADIATION ON METAL

MICROSTRUCTURE – TEM OBSERVATIONS OF METAL

| PAGE 8ASTM 18th Int. Symp. on Zr. in the Nuc. Ind., May 15-19, 2016, Hilton Head, SC, USA

Zircaloy-4 Unirradiated metal Zircaloy-4 Irradiated metal

• Formation of <a>-loops. No <c>-loops observed.

• No amorphization of the intermetallic precipitates

300 keV protons at 350°C. 4.6 dpa peak damage

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IMPACT OF IRRADIATION OF METAL ON CORROSION

KINETICS

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Damage profile

(calculated by SRIM)

Irradiated

Unirradiated

Time (days)

• Irradiation of the metal matrix leads to an early acceleration of corrosion.

• Transition occurs sooner in irradiated sample but at a similar oxide thickness.

• Post-transition corrosion rate slightly higher for the irradiated sample.

Corrosion kinetics

300 keV protons at 350°C

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IMPACT OF METAL IRRADIATION ON OXIDE

MICROSTRUCTURE - TEM OBSERVATIONS OF OXIDE

LAYERS (1/2)

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Zircaloy-4 Unirradiated sample Zircaloy-4 Oxide grown on irradiated metal

Many

cracks are

observed in

the oxide

layer grown

on an

irradiated

metal

matrix

300 keV

protons

at 350°C.

1018 /cm²

fluence.

4.6 dpa.

Corrosion:

30 days

Oxide

thickness:

1.2 µm

Corrosion:

14 days

Oxide

thickness:

1.5 µm

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IMPACT OF METAL IRRADIATION ON OXIDE

MICROSTRUCTURE - TEM OBSERVATIONS OF OXIDE

LAYERS (2/2)

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Zircaloy-4 Unirradiated sample Zircaloy-4 Oxide grown on irradiated metal

300 keV

protons

at 350°C.

1018 /cm²

fluence.

4.6 dpa.

Corrosion: 30 days

Oxide thickness: 1.2 µm

Corrosion: 14 days

Oxide thickness: 1.5 µm

• Observation of nano-sized pores ~100 nm below the oxide surface

in the irradiated sample.

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IMPACT OF METAL IRRADIATION ON OXIDE

MICROSTRUCTURE – XRD PATTERN

M (

-111)

M (

111)

M (

200)

M (

020)

T (

101)

T (

002) α

-Zr

(100)

α-Z

r(1

01)

α-Z

r(0

02)

XRD patterns close to oxide/metal interface

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| PAGE 13ASTM 18th Int. Symp. on Zr. in the Nuc. Ind., May 15-19, 2016, Hilton Head, SC, USA

Zircaloy-4 Unirradiated – 50 days – 1.4 µm oxide layer

EFFECT OF METAL IRRADIATION ON OXIDE

MICROSTRUCTURE – TETRAGONAL FRACTION (1/2)

oxide oxidemetal metal

t-ZrO2 =I(T(101))

I(T(101)) + I(M(111)) + I(M(-111))

• Increase of the tetragonal phase fraction across the oxide layer

• Average tetragonal fraction ~ 27%

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EFFECT OF METAL IRRADIATION ON OXIDE

MICROSTRUCTURE – TETRAGONAL FRACTION (2/2)

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• Uneven variations of tetragonal phase fraction across the oxide layer

which could be linked to local damage values

• Average tetragonal phase fraction ~18 %

Metal irradiation seems to lower the tetragonal phase fraction

Zircaloy-4 Irradiation of metal matrix 300keV protons 1018 ions/cm²

14 days - 1.5 µm oxide layer

oxide metal oxide metal

Page 15: MICROSTRUCTURE EVOLUTION IN ION- IRRADIATED …(compression and/or stoichiometry variations) o Irradiation of the oxide releases some of the compressive stresses in the monoclinic

IMPACT OF METAL IRRADIATION ON OXIDE

MICROSTRUCTURE – OXIDE D-SPACING

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Un

irra

dia

ted

sam

ple

Meta

l m

atr

ix i

rrad

iati

on

M(111)

M(-111)

T(101)

Unstressed

Unstressed

Unstressed

oxide metal oxide metal

oxide metal

oxide metal

oxide metal

oxide metal

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CONCLUSIONS METAL IRRADIATION

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The impact of metal irradiation on the corrosion kinetics and on the oxide

microstructure have been studied in this first part. The main results are:

What is the irradiation damage induced by the ion-irradiation of the metal matrix

o With our irradiation conditions: formation of <a>-loops. No amorphization of the

precipitates.

How are the corrosion kinetics affected by metal matrix irradiation?

o Increase of the corrosion kinetics for the irradiated sample. Transition occurs sooner

but at the same oxide thickness.

What is the microstructure of an oxide layer formed on an irradiated matrix?

o Lower tetragonal phase fraction for the irradiated sample.

o Lower d-spacing of the monoclinic phase: higher compressive stresses and/or

stoichiometry variation.

o Cracks observed in the oxide layer formed on the irradiated sample.

What does it mean in terms of corrosion mechanisms?

o If the oxide phase formed on irradiated metal is indeed more compressed: possible

stabilization of O vacancies by the inner compressive stress?

o Are we seeing stoichiometry variations in the irradiated sample (sub-oxide)?

Page 17: MICROSTRUCTURE EVOLUTION IN ION- IRRADIATED …(compression and/or stoichiometry variations) o Irradiation of the oxide releases some of the compressive stresses in the monoclinic

IMPACT OF OXIDE IRRADIATION ON

CORROSION BEHAVIOR

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ASTM 18th Int. Symp. on Zr. in the Nuc. Ind.,

May 15-19, 2016, Hilton Head, SC, USA

Page 18: MICROSTRUCTURE EVOLUTION IN ION- IRRADIATED …(compression and/or stoichiometry variations) o Irradiation of the oxide releases some of the compressive stresses in the monoclinic

IMPACT OF OXIDE IRRADIATION ON CORROSION

KINETICS

| PAGE 18ASTM 18th Int. Symp. on Zr. in the Nuc. Ind., May 15-19, 2016, Hilton Head, SC, USA

Damage profile

(calculated by SRIM)

Irradiated

Unirradiated

Time (days)

Corrosion kinetics

1.3 MeV He at 20°C

1017 ions/cm²

• Irradiation of the oxide layer induces an acceleration of corrosion.

• After 23 days of accelerated corrosion, the corrosion rate of the irradiated

sample follows that of the unirradiated one.

Reference

Irradiated oxide

Irradiated oxide re-oxidized 1 day

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IMPACT OF OXIDE IRRADIATION ON

MICROSTRUCTURE – TEM RESULTS

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Zircaloy-4 Unirradiated sample Zircaloy-4 Irradiated oxide layer

1.3 MeV

He ions

at 20°C.

1017 /cm²

fluence.

0.35 dpa.

Corrosion: 30 days

Oxide thickness: 1.2 µm

Corrosion: 50 days

Oxide thickness: 1.5 µm

• No major differences observed in irradiated oxide layer compared

to unirradiated oxide layer

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IMPACT OF OXIDE IRRADIATION ON

MICROSTRUCTURE – TETRAGONAL FRACTION

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Irradiated oxide Re-oxidized irradiated oxide (1day)

oxide metal oxide metal

oxide metaloxide metal

Avg.

fraction

~18%

Avg.

fraction

~23%

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IMPACT OF OXIDE IRRADIATION ON

MICROSTRUCTURE – OXIDE D-SPACING

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T(101)

M(111)

Unirradiated Irradiated oxide Re-oxidized

irradiated oxide

T(101) T(101)

M(111)M(111)

oxide metal

oxide metal

oxide metal

oxide metal

oxide metal

oxide metal

• Irradiation of the oxide seems to release some of the compressive

stresses in the monoclinic phase.

Page 22: MICROSTRUCTURE EVOLUTION IN ION- IRRADIATED …(compression and/or stoichiometry variations) o Irradiation of the oxide releases some of the compressive stresses in the monoclinic

CONCLUSIONS OXIDE IRRADIATION

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The impact of oxide irradiation on the corrosion kinetics and on the oxide

microstructure have been studied in this second part. The main results are:

How is the oxide microstructure affected by oxide irradiation?

o No major differences observed in TEM.

o The compressive stresses in the monoclinic phase are relaxed.

o Lower tetragonal phase fraction.

How does oxide irradiation affect the corrosion kinetics?

o Increase of the corrosion kinetics for the irradiated sample.

What is the microstructure of an oxide layer formed on an irradiated oxide?

o Most of the studied parameters are situated in between the irradiated oxide and the

unirradiated oxide even after 1 day of corrosion (tetragonal fraction, monoclinic

compressive stress).

What does it mean in terms of corrosion mechanisms?

o The defects induced by irradiation of the oxide layer are likely small, point-defects

o These defects have a strong impact on the corrosion kinetics but not so much on the

oxide microstructure.

Page 23: MICROSTRUCTURE EVOLUTION IN ION- IRRADIATED …(compression and/or stoichiometry variations) o Irradiation of the oxide releases some of the compressive stresses in the monoclinic

GENERAL CONCLUSIONS

| PAGE 23ASTM 18th Int. Symp. on Zr. in the Nuc. Ind., May 15-19, 2016, Hilton Head, SC, USA

The impact of irradiation on the corrosion kinetics and oxide microstructure have

been studied using TEM and synchrotron micro-diffraction of ion-irradiated samples.

The effects of the irradiation of the metal matrix and of the oxide layer have been

studied separately.

Common observations between metal irradiation and oxide irradiation:

o Ion-irradiation of the metal matrix and of the oxide layer both lead to an acceleration of

the corrosion kinetics.

o Irradiation induces a decrease of the tetragonal phase fraction.

Differences observed between metal irradiation and oxide irradiation

o Oxide formed on irradiated metal is severely cracked and presents a lower d-spacing

(compression and/or stoichiometry variations)

o Irradiation of the oxide releases some of the compressive stresses in the monoclinic

phase. No differences are observed in TEM: defects formed are likely point-defects.

The impact of irradiation of the metal and of the oxide is different in terms of oxide

microstructure but similar in terms of corrosion kinetics.

Page 24: MICROSTRUCTURE EVOLUTION IN ION- IRRADIATED …(compression and/or stoichiometry variations) o Irradiation of the oxide releases some of the compressive stresses in the monoclinic

NEXT STEPS

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Additional investigations can be performed on the oxide layers formed on an

irradiated metal matrix:

o Stress tensors can be derived from detailed refinement of µ-XRD data.

o Stoichiometry variations can be investigated (WDS, APT).

What happens when concurrent metal and oxide irradiation occur?

o Is there a synergistic effect?

o What is the impact of other parameters such as precipitate amorphization and

dissolution?

What about post-transition oxide layers? How are they affected by irradiation?

Are the results observed on ion-irradiated samples transferable to neutron-irradiated

samples?

Page 25: MICROSTRUCTURE EVOLUTION IN ION- IRRADIATED …(compression and/or stoichiometry variations) o Irradiation of the oxide releases some of the compressive stresses in the monoclinic

Direction de l’Energie Nucléaire

Département des Matériaux pour le Nucléaire

Service d’Etudes des Matériaux Irradiés

Commissariat à l’énergie atomique et aux énergies alternatives

Centre de Saclay | 91191 Gif-sur-Yvette Cedex

T. +33 (0)1 69 08 46 24 | F. +33 (0)1 69 08 90 73

Etablissement public à caractère industriel et commercial | RCS Paris B 775 685 019

| PAGE 25

ASTM 18th Int. Symp. on Zr. in the Nuc. Ind.,

May 15-19, 2016, Hilton Head, SC, USA