MICROSTRUCTURE EVOLUTION IN ION- IRRADIATED …(compression and/or stoichiometry variations) o...
Transcript of MICROSTRUCTURE EVOLUTION IN ION- IRRADIATED …(compression and/or stoichiometry variations) o...
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)
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]
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?
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
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
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
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
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
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
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
| 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%
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
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
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)?
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
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
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
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%
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.
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.
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.
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?
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
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ASTM 18th Int. Symp. on Zr. in the Nuc. Ind.,
May 15-19, 2016, Hilton Head, SC, USA