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INFLUENCE OF STEAM PRESSURE ON THE HIGH TEMPERATURE OXIDATION ANDTEMPERATURE OXIDATION AND POST-COOLING MECHANICAL PROPERTIES OF ZIRCALOY-4 AND M5™ CLADDING (LOCA CONDITIONS)
M. Le Saux1*, V. Vandenberghe1, P. Crébier2, J.C. Brachet1, D. Gilbon1, J.P. Mardon3, P. Jacques4, A. Cabrera4
1 CEA, DEN, 91191 Gif-sur-Yvette Cedex, France2 CEA, DEN, 38054 Grenoble Cedex 9, FranceCEA, DEN, 38054 Grenoble Cedex 9, France3 AREVA, AREVA NP SAS, Fuel Business Unit, 69546 Lyon Cedex 06, France4 EDF-SEPTEN, 69628 Villeurbanne Cedex, France*E-mail: [email protected]
17TH INTERNATIONAL SYMPOSIUM ON ZIRCONIUM IN THE NUCLEAR INDUSTRY, FEBRUARY 03-07, 2013, HYDERABAD, INDIA
20 FÉVRIER 2013 | PAGE 1M5™ is a trademark of AREVA NP registered in the USA and in other countries
INTRODUCTION
LOss of Coolant Accident (LOCA) in Light Water ReactorsLOss of Coolant Accident (LOCA) in Light Water Reactors
Zirconium alloys fuel claddings exposed to steam at High Temperature (HT, up to 1200°C) until quenching
Most studies focused on the Large Break LOCA conditions and thus performed at atmospheric pressure
Intermediate Break LOCA (IB-LOCA) conditions Core uncovery occurs at relativelyhigh primary pressure (several tens of bars up to ~80 bar)
Sometimes observed that steam pressure could have a significant effect on the HT oxidation of zirconium alloys
20 FÉVRIER 2013 | PAGE 217TH INTERNATIONAL SYMPOSIUM ON ZIRCONIUM IN THE NUCLEAR INDUSTRY, FEBRUARY 03-07, 2013, HYDERABAD
INTRODUCTION
Effect of steam pressure on the HT oxidation of Zr alloysEffect of steam pressure on the HT oxidation of Zr alloys
Scarce data and scattering and discrepancies from one study to another (e.g. Vrtilkova et al. (Nuclear Fuel Institute), Park et al. (Kyung Hee University)…)
Dependence on the oxidation temperature and the alloy (Zircaloy-4, E110, ZIRLO™…)
Oxide layer formed and hydrogen absorbed during in-service operation Potential influence on the steam pressure effect (burn-up dependence)
Origin of the steam pressure effect not clear so farOrigin of the steam pressure effect not clear so far
20 FÉVRIER 2013 | PAGE 317TH INTERNATIONAL SYMPOSIUM ON ZIRCONIUM IN THE NUCLEAR INDUSTRY, FEBRUARY 03-07, 2013, HYDERABAD
ZIRLO™ is a trademark of Westinghouse Electric.E110 is a trademark of A.A. Bochvar VNIINM.
INTRODUCTION
Main objectives of this studyMain objectives of this study
For low-tin Zircaloy-4 and M5™:
Influence of steam pressure (from 1 to 80 bar) on thep ( )oxidation and hydrogen pick-up at HT (between 750 and 1200°C) post-cooling mechanical properties
Impact on the steam pressure effect of representative in-servicehydriding (~ the end-of-life hydrogen contents expected for high BU cladding) oxidation (oxide layers thicknesses limited to 8 µm in this study)
20 FÉVRIER 2013 | PAGE 417TH INTERNATIONAL SYMPOSIUM ON ZIRCONIUM IN THE NUCLEAR INDUSTRY, FEBRUARY 03-07, 2013, HYDERABAD
OUTLINE
Materials and experimental procedureOxidation kinetics and hydrogen pick-upOxidation kinetics and hydrogen pick upOxide layer and oxygen diffusionMechanisms responsible for the steam pressure effect?ConclusionsConclusions
20 FÉVRIER 2013 | PAGE 517TH INTERNATIONAL SYMPOSIUM ON ZIRCONIUM IN THE NUCLEAR INDUSTRY, FEBRUARY 03-07, 2013, HYDERABAD
MATERIALS AND EXPERIMENTAL PROCEDURE
MaterialsMaterial Sn Fe Cr Nb O Zr
Nominal chemical composition (in wt.%)
Stress-Relieved Annealed low-tin Zircaloy-4 (Zy-4) and fullyrecrystallized M5™ cladding tube specimens (AREVA)
Zircaloy-4 1.3 0.2 0.1 - 0.13 Bal.
M5TM - 0.04 - 1.0 0.14 Bal.
Oxide Hydrogenspecimens (AREVA) Material State Oxidethickness
Hydrogencontent
Zircaloy-4
As-Received (AR) - -
Pre-hydrided - 500-600 wt.ppm
Pre oxidized 3 and 8 µm <100 wt ppmPre-oxidized 3 and 8 µm <100 wt.ppm
M5™
As-Received (AR) - -
Pre-hydrided - 190-230 wt.ppm
Pre-oxidized 3 and 5 µm <100 wt.ppm
20 FÉVRIER 2013 | PAGE 617TH INTERNATIONAL SYMPOSIUM ON ZIRCONIUM IN THE NUCLEAR INDUSTRY, FEBRUARY 03-07, 2013, HYDERABAD
MATERIALS AND EXPERIMENTAL PROCEDURE
MaterialsMaterial Sn Fe Cr Nb O Zr
Nominal chemical composition (in wt.%)
Stress-Relieved Annealed low-tin Zircaloy-4 (Zy-4) and fullyrecrystallized M5™ cladding tube specimens (AREVA)
Zircaloy-4 1.3 0.2 0.1 - 0.13 Bal.
M5TM - 0.04 - 1.0 0.14 Bal.
Oxide Hydrogenspecimens (AREVA)
Hydrogen charging in an argon/hydrogen mixture at 400°C (AREVA/CEZUS Paimboeuf)
Material State Oxidethickness
Hydrogencontent
Zircaloy-4
As-Received (AR) - -
Pre-hydrided - 500-600 wt.ppm
Pre oxidized 3 and 8 µm <100 wt ppm( ) Pre-oxidized 3 and 8 µm <100 wt.ppm
M5™
As-Received (AR) - -
Pre-hydrided - 190-230 wt.ppm
Pre-oxidized 3 and 5 µm <100 wt.ppm
20 FÉVRIER 2013 | PAGE 717TH INTERNATIONAL SYMPOSIUM ON ZIRCONIUM IN THE NUCLEAR INDUSTRY, FEBRUARY 03-07, 2013, HYDERABAD
MATERIALS AND EXPERIMENTAL PROCEDURE
MaterialsMaterial Sn Fe Cr Nb O Zr
Nominal chemical composition (in wt.%)
Stress-Relieved Annealed low-tin Zircaloy-4 (Zy-4) and fullyrecrystallized M5™ cladding tube specimens (AREVA)
Zircaloy-4 1.3 0.2 0.1 - 0.13 Bal.
M5TM - 0.04 - 1.0 0.14 Bal.
Oxide Hydrogenspecimens (AREVA)
Hydrogen charging in an argon/hydrogen mixture at 400°C (AREVA/CEZUS Paimboeuf)
Material State Oxidethickness
Hydrogencontent
Zircaloy-4
As-Received (AR) - -
Pre-hydrided - 500-600 wt.ppm
Pre oxidized 3 and 8 µm <100 wt ppm( )
Two-side pre-oxidation in staticautoclave at 360°C with typicalPWR primary water chemistry
Pre-oxidized 3 and 8 µm <100 wt.ppm
M5™
As-Received (AR) - -
Pre-hydrided - 190-230 wt.ppm
Pre-oxidized 3 and 5 µm <100 wt.ppm
(1000 ppm B, 2.2 ppm Li and 30 cc/kg H2) (EDF R&D)
Pre-transient oxide layers homogeneouslysmooth and black/dark grey
20 FÉVRIER 2013 | PAGE 817TH INTERNATIONAL SYMPOSIUM ON ZIRCONIUM IN THE NUCLEAR INDUSTRY, FEBRUARY 03-07, 2013, HYDERABAD
MATERIALS AND EXPERIMENTAL PROCEDURE
High temperature oxidation and coolingcooling
Double-side oxidation in a flowing steam environment in the CINOG HP facility (CEA)
Steam inlet
Oxidation temperatures (T): 750, 850, 900, 1000, 1100 and 1200°CSteam pressures (P): 1, 10, 20, 40, 60 and 80 barOxidation times (t): 200, 400, 600, 1800, 3600, Condenser
Sample and quartz tube
( ) , , , , ,7200, 9000 and 18000s
Cooling, quite fast (~100-150°C/s down to 500°C) but slower than during a direct water quenchingg q g
20 FÉVRIER 2013 | PAGE 917TH INTERNATIONAL SYMPOSIUM ON ZIRCONIUM IN THE NUCLEAR INDUSTRY, FEBRUARY 03-07, 2013, HYDERABAD
OUTLINE
Materials and experimental procedureOxidation kinetics and hydrogen pick-upOxidation kinetics and hydrogen pick upOxide layer and oxygen diffusionMechanisms responsible for the steam pressure effect?ConclusionsConclusions
20 FÉVRIER 2013 | PAGE 1017TH INTERNATIONAL SYMPOSIUM ON ZIRCONIUM IN THE NUCLEAR INDUSTRY, FEBRUARY 03-07, 2013, HYDERABAD
OXIDATION KINETICS AND HYDROGEN PICK-UP
At atmospheric pressureResults in good agreement with data previously 10
15
cm2 )
Zy-4, 1 bar1100 C
1000 C
1200 C
g g p yobtained in other CEA facilities
Oxidation kinetics sub-parabolic (n≈2.6) between 700 and 900°C and nearly parabolic (n≈2) b t 1000 d 1400°C
5
10
Wei
ght g
ain
(mg/
c
900 C
1000 C
― CINOG BP- - DEZIROX 1Symbols: This study
between 1000 and 1400°C
Oxidation kinetics faster for fresh Zy-4 than for fresh M5™ for T below 1100°C, nearly the same f b th t i l t hi h T
nKtWg 1
00 1000 2000 3000 4000
W
Oxidation time (s)
850 C750 C
15M5™, 1 bar1100 Cfor both materials at higher T
For both materials, Wg lower than those predicted by the Baker-Just (BJ) correlation whatever T, not far from the Cathcart-Pawel (CP) correlation
10
ain
(mg/
cm2 )
1000 C
1200 C ― CINOG BP- - DEZIROX 1Symbols: This study
far from the Cathcart Pawel (CP) correlation beyond 1000-1100°C and lower below
No hydrogen uptake at HT (pre-breakaway oxidation regime)
0
5
Wei
ght g
a850 C750 C
900 C
1000 C
20 FÉVRIER 2013 | PAGE 1117TH INTERNATIONAL SYMPOSIUM ON ZIRCONIUM IN THE NUCLEAR INDUSTRY, FEBRUARY 03-07, 2013, HYDERABAD
00 1000 2000 3000 4000
Oxidation time (s)
OXIDATION KINETICS AND HYDROGEN PICK-UP
Effect of P on fresh Zy-4 (1/3)
6
g/cm
2 )
Zy-4, 850 C
600BJ 1800s
BJ 3600s 1800s
3600s
750-1000°C: Oxidation kinetics enhanced under high P, since the early stages of oxidation (≤200s)
Wei
ght g
ain
(mg
200s
600s
BJ 200s
BJ 600s
P
oxidation (≤200s) Wg under high P (>60 bar) slightly greater thanthose predicted by the BJ correlation
1100 and 1200°C: Effect of P quite low or
0.60 20 40 60 80
Steam pressure (bar)20Zy-4, 1100 C
1100 and 1200°C: Effect of P quite low or negligible
No significant effect of P on the exponent n of th l id ti ki ti d l ga
in (m
g/cm
2 )
200s
400s
BJ 200s
BJ 400s
P
the general oxidation kinetics model
2W
eigh
t g
200s
20 FÉVRIER 2013 | PAGE 1217TH INTERNATIONAL SYMPOSIUM ON ZIRCONIUM IN THE NUCLEAR INDUSTRY, FEBRUARY 03-07, 2013, HYDERABAD
20 20 40 60 80
Steam pressure (bar)
OXIDATION KINETICS AND HYDROGEN PICK-UP
Effect of P on fresh Zy-4 (2/3) 1exp,, PtTPtTWg
Park et al.
Dependency of Wg on P nearly exponential
P effect increases with increasing t
1,exp1,,
PtTtTWg
Steam pressure effectparameter
P effect increases with increasing t, significantly at the beginning of oxidation and slower after (kind of saturation as the oxidegrowths) 0.6
0.8
1
essu
re e
ffect
α
(-) 900 C
850 CZy-4
1000 C
P effect maximal at 850°C but does not change so much between 750 and 1000°C
0
0.2
0.4
0 1000 2000 3000 4000mal
ized
stea
m p
repa
ram
eter
, α
750 C
1100 C1200 C
t
-0.4
-0.2
Nor
mOxidation time (s)
20 FÉVRIER 2013 | PAGE 1317TH INTERNATIONAL SYMPOSIUM ON ZIRCONIUM IN THE NUCLEAR INDUSTRY, FEBRUARY 03-07, 2013, HYDERABAD
OXIDATION KINETICS AND HYDROGEN PICK-UP
Effect of P on fresh Zy-4 (3/3)
300
350
pm)
Zy-4Increase of Wg with increasing P associated witha significant but limited hydrogen pick-up
150
200
250
en co
nten
t (w
t.pp
80 bar
The higher the P, the greater the hydrogenuptake (no hydrogen uptake at 1 bar)
Hydrogen uptake increases during oxidationP
t
0
50
100
0 10 20 30 40 50 60 70
Hyd
rog
1 bar
40 barHydrogen pick-up fraction relatively low (ratio of hydrogen absorbed by the material and hydrogenreleased during oxidation <10%)
P
0 10 20 30 40 50 60 70(Oxidation time (s))1/2
20 FÉVRIER 2013 | PAGE 1417TH INTERNATIONAL SYMPOSIUM ON ZIRCONIUM IN THE NUCLEAR INDUSTRY, FEBRUARY 03-07, 2013, HYDERABAD
OXIDATION KINETICS AND HYDROGEN PICK-UP
6
g/cm
2 )
M5™, 850 C
BJ 1800s
BJ 3600s
3600s
7200sEffect of P on fresh M5™
Wei
ght g
ain
(mg
600s
BJ 200s
BJ 600s
1800s
3600s
750-1200°C: P effect quite low or negligible Wg lower than those predicted by the BJ correlation P
0.60 20 40 60 80
Steam pressure (bar)
200s
BJ 200s
20M5™, 1100 C
correlation
No significant effect of P on the exponent nof the general oxidation kinetics model
gain
(mg/
cm2 )
400sBJ 200s
BJ 400s
No significant hydrogen uptake whateverthe oxidation conditions P
2W
eigh
t g
200s
20 20 40 60 80
Steam pressure (bar)
20 FÉVRIER 2013 | PAGE 1517TH INTERNATIONAL SYMPOSIUM ON ZIRCONIUM IN THE NUCLEAR INDUSTRY, FEBRUARY 03-07, 2013, HYDERABAD
OXIDATION KINETICS AND HYDROGEN PICK-UP
Effect of pre-hydriding at 850 and 1000°C
10
g/cm
2 )
FreshPre-H. 600 wt.ppm
Zy-4
1000 Cand 1000°C
For both Zy-4 and M5™, no significant impact of pre transient hydriding ( h i ) up
Wei
ght g
ain
(mg
1000 C200s
400s
of pre-transient hydriding (gaseous charging) up to end-of-life hydrogen contents on the
oxidation kineticshydrogen uptaket ff t
10 20 40 60 80
Steam pressure (bar)
850 C600s
10FreshPre-H 150 wt ppm
M5™steam pressure effect
P effect important for Zy-4 and much less significant for M5™, whether the material is pre-hydrided or not ga
in (m
g/cm
2 )
Pre-H. 150 wt.ppm
1000 C400spre-hydrided or not
1W
eigh
t g
850 C600s
1000 C200s
20 FÉVRIER 2013 | PAGE 1617TH INTERNATIONAL SYMPOSIUM ON ZIRCONIUM IN THE NUCLEAR INDUSTRY, FEBRUARY 03-07, 2013, HYDERABAD
10 20 40 60 80
Steam pressure (bar)
OXIDATION KINETICS AND HYDROGEN PICK-UP
Effect of a thin pre-oxide layer at 850 and 1000°C (1/2)
Pre-ox β (+α )t
10
g/cm
2 )
FreshPre-ox. ~3 µmPre-ox. ~8 µmBJCP
Zy-4, 1000 C, 400s
FreshBJCP
For both materials, for the same ox. conditions under 1 or 80 bar, Wg lower for the pre-oxidized samples (the
Pre-ox.
O2
Stea
m
βZr (+αZr)t0
Wei
ght g
ain
(mg
Pre-ox. ~3 µm
P
CP
pre oxidized samples (the thicker the pre-ox. layer, the greater the decrease in Wg), at least for short t St
eam OO2
αZr(O)Pre-ox. βZr (+αZr)HT ox.t1>t0
10 20 40 60 80
Steam pressure (bar)
Pre-ox. ~8 µm
P
10FreshPre-ox. ~3 µm
M5™, 1000 C, 400s
Wg of pre-ox. materials substantially lower than those predicted by the CP and BJ correlations, even for P as high as 80 bar
gain
(mg/
cm2 )
Pre ox. 3 µmPre-ox. ~5 µmBJCP
Fresh
BJCP
In the case of pre-ox. materials, for a given pre-oxide layer thickness, Wg of M5™ close to those of Zy-4, whereas lower in the case of non pre-ox. materials (decrease in Wg due to pre-ox. lower for M5™ 1
Wei
ght g Pre-ox. ~3 µm
Pre-ox. ~5 µm
P
20 FÉVRIER 2013 | PAGE 1717TH INTERNATIONAL SYMPOSIUM ON ZIRCONIUM IN THE NUCLEAR INDUSTRY, FEBRUARY 03-07, 2013, HYDERABAD
a e a s ( g pthan for Zy-4 for the conditions investigated)
10 20 40 60 80
Steam pressure (bar)
OXIDATION KINETICS AND HYDROGEN PICK-UP
Effect of a thin pre-oxide layer at 850 and 1000°C (2/2)
0.6
0.8
1
essu
re e
ffect
(-)
Zy-4
--- 850 C 600s― 1000 C 400s
P effect on the oxidation of Zy-4 reduced in the presence of a thin pre-oxide layer
Differences between sensitivities of Zy-4 and0
0.2
0.4
0 2 4 6 8rmal
ized
stea
m p
repa
ram
eter
, α
Differences between sensitivities of Zy-4 and M5™ to P significantly smaller after pre-oxidation
For the same oxidation conditions, hydrogen pick-up of pre-oxidized Zy-4 under 80 bar (no hydrogen
-0.4
-0.2Nor
Pre-oxide thickness (µm)
M5™
180
2001 barZy-4up o p e o d ed y u de 80 ba ( o yd oge
uptake at 1 bar) lower than those of the fresh or pre-hydrided material, in correlation with the lower Wg
100
120
140
160
180
ck-u
p (w
t.ppm
) 80 barZy 4
850 C80 bar
No significant hydrogen uptake at HT in the case of pre-oxidized M5™
20
40
60
80
Hyd
roge
n pi
c
1000 C80 bar
1 b
FreshPre-ox.~3µm
20 FÉVRIER 2013 | PAGE 1817TH INTERNATIONAL SYMPOSIUM ON ZIRCONIUM IN THE NUCLEAR INDUSTRY, FEBRUARY 03-07, 2013, HYDERABAD
00 2 4 6 8 10
Weight gain (mg/cm2)
1 bar
OUTLINE
Materials and experimental procedureOxidation kinetics and hydrogen pick-upOxidation kinetics and hydrogen pick upOxide layer and oxygen diffusionMechanisms responsible for the steam pressure effect?ConclusionsConclusions
20 FÉVRIER 2013 | PAGE 1917TH INTERNATIONAL SYMPOSIUM ON ZIRCONIUM IN THE NUCLEAR INDUSTRY, FEBRUARY 03-07, 2013, HYDERABAD
OXIDE LAYER AND OXYGEN DIFFUSION
Oxide and metallic layersthicknesses
1 bar 80 bar
FreshM5™
Oxidelayer
Oxidelayer
Measured oxide layers thicknesses in accordance with Wg:
not significantly modified by the increase
M5™
Oxidelayer
Oxidelayer
1
not significantly modified by the increase in P at 850, 1000 or 1200°C for M5™ increase with increasing P at 850 and 1000°C but not at 1200°C for Zy-4 25 µm
FreshZy-4
0.6
0.7
0.8
0.9
1
conc
entra
tion
(-)
1 bar80 bar
Zy-4850 C 3600s
Enhanced oxidation kinetics of Zy-4 under high Pat 850 and 1000°C not associated with additional oxygen diffusion through the metallic substrate
0.1
0.2
0.3
0.4
0.5
Nor
mal
ized
oxy
gen
1 bar 80 bar
metallic substrate
00 50 100 150 200 250 300
N
Distance from the initial outer surface (µm)20 FÉVRIER 2013 | PAGE 2017TH INTERNATIONAL SYMPOSIUM ON ZIRCONIUM IN THE NUCLEAR INDUSTRY, FEBRUARY 03-07, 2013, HYDERABAD
OXIDE LAYER AND OXYGEN DIFFUSION
Morphology of the oxide layers
For both materials whatever T and PFor both materials, whatever T and P, columnar structure of the oxide
M5™: No significant effect of P on the morphology, porosity or damage of oxide
1 bar 80 bar
FreshM5™morphology, porosity or damage of oxide
layers formed between 750 and 1200°C
Zy-4: Oxides formed under high Pbetween 750 and 1000°C
M5™
are more “stratified” and exhibitmore pores and cracks show crystallites smaller and more disorganized and disoriented with
FreshZy-4
2 µm
Observations performed aftercooling and mechanical testing Additional pores and cracks
disorganized and disoriented with grain boundaries not defined as well as in the oxides formed at 1 bar
2 µm
20 FÉVRIER 2013 | PAGE 2117TH INTERNATIONAL SYMPOSIUM ON ZIRCONIUM IN THE NUCLEAR INDUSTRY, FEBRUARY 03-07, 2013, HYDERABAD
OUTLINE
Materials and experimental procedureOxidation kinetics and hydrogen pick-upOxidation kinetics and hydrogen pick upOxide layer and oxygen diffusionMechanisms responsible for the steam pressure effect?ConclusionsConclusions
20 FÉVRIER 2013 | PAGE 2217TH INTERNATIONAL SYMPOSIUM ON ZIRCONIUM IN THE NUCLEAR INDUSTRY, FEBRUARY 03-07, 2013, HYDERABAD
MECHANISMS RESPONSIBLE FOR THE STEAM PRESSURE EFFECT?
Mechanisms inherent to the P effect take place at the early stage of oxidationMechanisms inherent to the P effect take place at the early stage of oxidation
Oxidation mechanisms not fundamentally ≠ under high P and atmospheric P
Influence of P on the reaction at the outer oxide/steam interface and/or on the oxygen transport through the existing oxide but not on the reaction at the inner M/Ooxygen transport through the existing oxide but not on the reaction at the inner M/O interface and the oxygen diffusion beneath it
Alloy dependent influence of P on the microstructure of the oxide formed at HT (and thus on the oxygen diffusion through it) but not really on the oxygen transport rate yg g ) y yg pthrough the pre-existing scale (rate limiting process until complete reduction of the pre-oxide)
Oxide layer formed under high P still partially protective
20 FÉVRIER 2013 | PAGE 2317TH INTERNATIONAL SYMPOSIUM ON ZIRCONIUM IN THE NUCLEAR INDUSTRY, FEBRUARY 03-07, 2013, HYDERABAD
MECHANISMS RESPONSIBLE FOR THE STEAM PRESSURE EFFECT?
Oxide morphology, porosity and cracking
P effect associated with a faster development within the oxides formed under high P of porosities and micro-cracks Easier access of oxygen and hydrogen atoms to the metallic substrate
Oxide grains morphology and orientation modified under high P Steam diffusion and pores formation at grain boundaries and inter-granular cracking facilitatedfacilitated
20 FÉVRIER 2013 | PAGE 2417TH INTERNATIONAL SYMPOSIUM ON ZIRCONIUM IN THE NUCLEAR INDUSTRY, FEBRUARY 03-07, 2013, HYDERABAD
MECHANISMS RESPONSIBLE FOR THE STEAM PRESSURE EFFECT?
Oxide phases and stoichiometry and metallic substrate
Potential influence of P on the stability of the tetragonal phase of zirconia (metastable below 1000°C) and/or on the tetragonal to monoclinic phase transformation Additional stresses and formation of pores or even cracks
Eff t f P th id t i hi t ( i ) M i fl tEffect of P on the oxide stoichiometry (oxygen vacancies) May influence atoms diffusion through the oxide, stability of zirconia tetragonal phase and/or oxide plasticity (sometimes, whitish color of the outer surface of the oxide layers formed on Zy-4 under high P)
P effect potentially related to the evolution of the characteristics and the resultingP effect potentially related to the evolution of the characteristics and the resultingproperties of the metallic substrate, in particular at the beginning of the ox. process(750-1000°C: metallic substrate in αZr phase or two-phases (αZr+βZr) + dissolution of someintermetallic precipitates in Zy-4 and apparition of Nb-enriched βZr phase in M5™)
20 FÉVRIER 2013 | PAGE 2517TH INTERNATIONAL SYMPOSIUM ON ZIRCONIUM IN THE NUCLEAR INDUSTRY, FEBRUARY 03-07, 2013, HYDERABAD
OUTLINE
Materials and experimental procedureOxidation kinetics and hydrogen pick-upOxidation kinetics and hydrogen pick upOxide layer and oxygen diffusionMechanisms responsible for the steam pressure effect?ConclusionsConclusions
20 FÉVRIER 2013 | PAGE 2617TH INTERNATIONAL SYMPOSIUM ON ZIRCONIUM IN THE NUCLEAR INDUSTRY, FEBRUARY 03-07, 2013, HYDERABAD
CONCLUSIONS
Oxidation kinetics and hydrogen pick-up
U d hi h P b t 750 d 1000°C id ti ki ti f f b i t d lUnder high P between 750 and 1000°C, oxidation kinetics of as-fabricated low-tin Zy-4 enhanced and combined with a significant but limited hydrogen uptake since the early stages of oxidation
P effect quite low or negligible between 750 and 1000°C for as-fabricatedP effect quite low or negligible between 750 and 1000 C for as-fabricated M5™, and at 1100 and 1200°C for both alloys
P has potentially an effect on the oxidation rate but does not really modify the (sub-) parabolic oxidation kineticsp
Oxidation kinetics, hydrogen uptake and effect of P not significantly modified by in-service pre-hydriding (gaseous charging) up to the end-of-life hydrogen contents expected for Zy-4 and M5™
Weight gains at 850 and 1000°C lower for materials with thin pre-oxide layers (3 to 8 µm thick, formed in autoclave at 360°C with typical PWR primary water chemistry) and ≠ between sensitivities of Zy-4 and M5™ to P significantly reduced after pre-ox. i th thi k i ti t d
20 FÉVRIER 2013 | PAGE 2717TH INTERNATIONAL SYMPOSIUM ON ZIRCONIUM IN THE NUCLEAR INDUSTRY, FEBRUARY 03-07, 2013, HYDERABAD
in the thickness range investigated
CONCLUSIONS
Oxide layer, oxygen diffusion and mechanismspotentially responsible for the P effect
Enhanced oxidation kinetics of Zy-4 under high P correlated with a thickening of the oxide layers formed at HT but not associated with additional oxygen diffusion through the metallic substratediffusion through the metallic substrate
P has an influence on the microstructure (crystallites morphology, porosity and cracks) of the oxide formed within the 750-1000°C T range on Zy-4, but not on M5™
Assumptions: Changes in oxide microstructure, probably responsible for a faster oxygen (and hydrogen) transport through the oxide layer, potentially induced by a destabilization promoted under high P of the tetragonal phase of zirconia?
20 FÉVRIER 2013 | PAGE 2817TH INTERNATIONAL SYMPOSIUM ON ZIRCONIUM IN THE NUCLEAR INDUSTRY, FEBRUARY 03-07, 2013, HYDERABAD
CONCLUSIONS
Post-cooling mechanical properties and P effect consequences during in-reactor transients
Effect of P on the post-cooling mechanical properties (ring compression tests at 20 and 135°C) of fresh, pre-hydrided and pre-oxidized Zy-4 and M5™ oxidized at HT
ll li it d f th diti i ti t dgenerally limited for the conditions investigated
According to calculations, impact of the P effect for Zy-4 very low or negligible on the ECR actually achieved during typical in-reactor transientsy g yp No consequence on LOCA related criteria verification
20 FÉVRIER 2013 | PAGE 2917TH INTERNATIONAL SYMPOSIUM ON ZIRCONIUM IN THE NUCLEAR INDUSTRY, FEBRUARY 03-07, 2013, HYDERABAD
Thank you for your attention
Direction de l’Energie NucléaireCommissariat à l’énergie atomique et aux énergies alternatives
| PAGE 30
17TH INTERNATIONAL SYMPOSIUM ON Direction de l Energie NucléaireDépartement des Matériaux pour le NucléaireService de Recherches Métallurgiques Appliquées
Commissariat à l énergie atomique et aux énergies alternativesCentre de Saclay | 91191 Gif-sur-Yvette CedexT. +33 (0)1 69 08 12 28 | F. +33 (0)1 69 08 71 67
Etablissement public à caractère industriel et commercial | RCS Paris B 775 685 01920 FÉVRIER 2013
17TH INTERNATIONAL SYMPOSIUM ON ZIRCONIUM IN THE NUCLEAR INDUSTRY, FEBRUARY 03-07, 2013, HYDERABAD