characterization of oxygen distribution in loca …€¦ · distribution in loca situations duriez...
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CHARACTERIZATION OF OXYGENDISTRIBUTION IN LOCA SITUATIONS
Duriez C.1, Guilbert S.1 , Stern A.2, Grandjean C.1, Bělovský L.3, Desquines J.1
1 IRSN
² IRSN post-doctorate, now at CEA
3 ALIAS Cz
16th International Symposium on the Zirconium in the Nuclear Industry – Chengdu, China 2/ 22
Scope of the presentation•DIFFOX:
IRSN develops a simulation code aiming at modeling the oxygen profile within acladding submitted to a LOCA transient.
•Validation of High Temperature oxidation Process:
Oxidation kinetics and oxygen content profile compared to literature data
Two main areas for DIFFOX improvement have been studied:
•Low Temperature oxide dissolution process:
Influence from bare up to 70 microns thick LT oxide layer
•Influence of hydrogen on the Zy-O phase diagram:
Effect of 600 ppm hydrogen content on the a/a+b and a+b/b transus
16th International Symposium on the Zirconium in the Nuclear Industry – Chengdu, China 3/ 22
DIFFOX: main modeling options of the code
b(O
)-Zr
a(O
)+b(
O)-
Zr
a(O
)-Zr
ZrO
2 • Single and two-sided oxidation,
• Thermal transients modeled,• Solving of diffusion equation with movingboundaries (1D, implicit finite differences),• LT and HT oxide layers modeled,
• Partial dissolution of LT oxide layer duringthe HT transient,
• ZrO2, a(O)-Zr, b(O)-Zr , a(O)+b(O)-Zr layersmodeled,
• Diffusion coefficients mainly derived from literature review,
• Influence of hydrogen on Zy-O phase diagram boundaries modeled:
latest DIFFOX version
Expectedinfluence of H
500
700
900
1100
1300
1500
0 1 2 3 4O (Wt %)
Tem
pera
ttur
e (°
C)
a Zr
b Zr a+b
Zr
5
[H]=0[H]≠0
LT-Z
rO2
HT-
ZrO
2
16th International Symposium on the Zirconium in the Nuclear Industry – Chengdu, China 4/ 22
DIFFOX: Oxide scale modeling
The development and validation of DIFFOX are major issue for IRSNValidation on Leistikow 650-1400°C isothermal tests (1987)
t-ZrO2
oxide (total ZrO2 thickness)
oute
r oxi
de s
urfa
ce
tetr
agon
alsu
b-la
yer
(<12
00°C
)
bulk oxide pre-oxide
high-temperature oxide low-temperature oxide
Met
al
monoclinic (<850 °C)or
mon + tet (850-1200 °C)or
tetragonal (>1200 °C)
monoclinic (<1100 °C)or
mon + tet (>1100 °C)
t-ZrO2
oxide (total ZrO2 thickness)
oute
r oxi
de s
urfa
ce
tetr
agon
alsu
b-la
yer
(<12
00°C
)
bulk oxide pre-oxide
high-temperature oxide low-temperature oxide
Met
al
monoclinic (<850 °C)or
mon + tet (850-1200 °C)or
tetragonal (>1200 °C)
monoclinic (<1100 °C)or
mon + tet (>1100 °C)
16th International Symposium on the Zirconium in the Nuclear Industry – Chengdu, China 5/ 22
Zirconium alloy:Stress Relieved Annealed (SRA) low-tin Zircaloy-4 tubes from CEZUS
Low Temperature (LT) corrosion:• Specimens were LT pre-oxidized at 500°C under pure oxygen to assess theinfluence of in-service corrosion
• 10 to 60 days exposure leading to 10 to 70 micrometers thick pre-oxide layers
Hydriding:• 600 wppm electrolytic hydriding of 50 cm long samples performed at EDF (160h)• Hot extraction at 4 different locations confirmed values ranging between 575-640ppm.• 24 h at 430°C heat treatment to achieve a quite uniform H distribution
Tested materials
100 µm
Example:60 days exposure
Polarized lightBright light
16th International Symposium on the Zirconium in the Nuclear Industry – Chengdu, China 6/ 22
High Temperature oxidation: protocol validation on bare Zy-4
ArSteam generator
sample
Ar
Sample holderwith alumina
furnace
quenching bath(water)
Vertical furnace for HToxidation
The HT oxidation protocol gives oxidation kinetics consistent with literaturedata between 900 and 1200°C for a wide range of oxidation durations
Comparison to literature data
0
50
100
150
200
0 1000 2000 3000 4000 5000 6000
Durations (s)
Wei
ght g
ain
(g/m
²)900°C
1000°C
1100°C1200°C
Billone 2008 (US-NRC)
present study
Hozer 2008 (KFKI)Ozawa 2000 (NDC)Kawasaki 1978 (JAERI)Brachet 2001 (CEA)
Billone 2008 (US-NRC)
present study
Hozer 2008 (KFKI)Ozawa 2000 (NDC)Kawasaki 1978 (JAERI)Brachet 2001 (CEA)
Cathcart-Pawelcorrelation
16th International Symposium on the Zirconium in the Nuclear Industry – Chengdu, China 7/ 22
HT dissolution of the LT oxide layer
16th International Symposium on the Zirconium in the Nuclear Industry – Chengdu, China 8/ 22
HT dissolution of the LT oxide layer: main objectivesSafety concern:
The HT dissolution of the LT oxide layer potentially induces significant oxygencharging in the sample and can have a deleterious impact on the Post-Quench-Ductility.
DIFFOX:The DIFFOX code has the potential of simulating this LT oxide layer dissolution butrequires validation data.
Experiments performed for validation of DIFFOX LT oxide layer dissolution modeling:•HT vacuum annealing of pre-oxidized samples (maximizing the dissolution process),
•HT steam annealing of pre-oxidized samples (competition between HT oxidation andHT dissolution).
HT conditions (900°C-6000s):•At the present stage experimental conditions don’t address the LOCA safety issue butthe DIFFOX validation issue.
•The HT heat treatment is chosen to enhance dissolution of the LT oxide.
16th International Symposium on the Zirconium in the Nuclear Industry – Chengdu, China 9/ 22
• Oxidation:
• Post-quench optical metallography:
• ZrO2 and aZr(O): layer thickness measurement at 8 angular locations (both:inner and outer layers): eZrO2 = 18.5 ± 0.7 mircons
eaZr(O)= 34.5 ± 1.0 microns
• EPMA radial O concentration profiles and O distribution maps (O Ka line)
• Average H content measurements in the sample by hot extraction : negligible
High Temperature oxidation of as-received samples
100 µm100 µm 100 µm100 µm
no LT oxtime
temperatureHT: 900°C – 6000 s
As received Zy-4 + HT oxidation
A similar procedure was systematically applied to all tested samples
steam
16th International Symposium on the Zirconium in the Nuclear Industry – Chengdu, China 10/ 22
•Oxidation:
•Post-quench optical metallography:
•ZrO2 and aZr(O): layer thickness measurement at 8 angular locations (both:inner and outer layers): DeZrO2 = - 5 to -10 microns
eaZr(O) ~ 35.0 microns
500°C LT ox
time
temperatureHT: 900°C – 6000 s
Pre-oxidized + HT vacuum ann.vacuum
HT Dissolution of the LT oxide layer: HT vacuum annealing
Oxygen
50 mm
10 mm LT ZrO2 20 mm LT ZrO2 30 mm LT ZrO2 40 mm LT ZrO2 60 mm LT ZrO2 70 mm LT ZrO2
16th International Symposium on the Zirconium in the Nuclear Industry – Chengdu, China 11/ 22
•Oxidation:
•Post-quench optical metallography:
•ZrO2 and aZr(O): layer thickness measurementDeZrO2 ~ -5 microns DeZrO2 = +20 micronseaZr(O) ~ 40.0 microns eaZr(O) ~ 30.0 microns
500°C LT ox
time
temperatureHT: 900°C – 6000 s Pre-oxidized + HT oxidation
steam
HT Dissolution of the LT oxide layer: HT steam oxidation
Oxygen
Example: 20 mm LT ZrO2
0.5 mm
25 mm
dark–brownregions
light–brownregions
HT oxide
LT oxideLT oxide
25 mm
16th International Symposium on the Zirconium in the Nuclear Industry – Chengdu, China 12/ 22
HT Dissolution of the LT oxide layer: DIFFOX vs experiments20 mm LT ZrO2 followed by HT steam oxidation (900°C – 6000 s)
• DIFFOX predicts a protective LT ZrO2 layer• No HT oxide expected,• aZr(O) layer thickness over-predicted in regions with HT oxide
Oxy
gen
conc
entr
atio
n (w
t%)
Oxy
gen
conc
entr
atio
n (
Oxy
gen
conc
entr
atio
n (
0
5
10
15
20
25
30
0 50 100 150 200
DIFFOX simulation
MeasuredO-profile:20 mm LT ZrO2 + HT steam oxidized
DIFFOX simulation
MeasuredO-profile:20 mm LT ZrO2 + HT steam oxidized
DIFFOX simulation
MeasuredO-profile:20 mm LT ZrO2 + HT steam oxidized
Distance to outer surface (µm) Distance to outer surface (µm)O
xyge
n co
ncen
trat
ion
(wt%
)0 50 100 150 200
DIFFOX simulation
MeasuredO-profile:20 mm LT ZrO2 + HT steam oxidized
DIFFOX simulation
MeasuredO-profile:20 mm LT ZrO2 + HT steam oxidized
0
5
10
15
20
25
30Region with no HT oxide Region with HT oxide
16th International Symposium on the Zirconium in the Nuclear Industry – Chengdu, China 13/ 22
HT Oxidation of as-received samples: DIFFOX vs experimentsAs-received cladding HT steam oxidation (900°C – 6000 s)
Very good code-to-data agreementPolishing reveals only part of the aZr(O) region
0
5
10
15
20
25
30
0 50 100 150 200
Distance to outer surface (µm)
Oxy
gen
conc
entr
atio
n (w
t%) DIFFOX simulation
Measured O- profile:as- received + HT steam oxidized
DIFFOX simulation
Measured O- profile:as- received + HT steam oxidized
16th International Symposium on the Zirconium in the Nuclear Industry – Chengdu, China 14/ 22
HT Dissolution of the LT oxide layer: DIFFOX vs experiments20 mm LT ZrO2 followed by HT vacuum anneal (900°C – 6000 s)
Very good code-to-data agreement
0
5
10
15
20
25
30
0 50 100 150 200
Distance to outer surface (µm)
Oxy
gen
conc
entr
atio
n (w
t%) DIFFOX simulation
Measured O- profile:20 mm LT ZrO2 + HT vacuum annealed
DIFFOX simulation
Measured O- profile:20 mm LT ZrO2 + HT vacuum annealed
16th International Symposium on the Zirconium in the Nuclear Industry – Chengdu, China 15/ 22
Investigating the Influence of Hon Zy-O phase diagram
16th International Symposium on the Zirconium in the Nuclear Industry – Chengdu, China 16/ 22
Expected influence of Hydrogen on the oxygen distribution
•Hydrogen shifts the a/(a+b) and b/(a+b) boundaries to higher Oconcentrations:
O solubility in the bZr phase is increased•Few experiments addressing influence of hydrogen,•It was thus decided to improve the description of this effect in DIFFOX code.
500
700
900
1100
1300
1500
0 1 2 3 4
O (Wt %)
Tem
pera
tture
(°C)
a Zr(O)
b Zr a+
b Zr
5
[H]=0
[H]≠0
O content
Distance to the outer surface
ZrO
2 aZr(
O)
bZr
[H]➷[H]➹
16th International Symposium on the Zirconium in the Nuclear Industry – Chengdu, China 17/ 22
Strategy to evaluate the influence of 600 ppm H
• (a+b) phase tests• a phase tests• 3 temperatures
21 samples tested
500
600
700
800
900
1000
1100
1200
1300
1400
1500
0 1 2 3 4O (wt%)
Tem
pera
ture
( °C)
Expected influenceof 600 wt ppm H
[H]=
0a
bZra+b Zr
51.3 2.0 5.0
a+b Zr expecteda Zr expected
500
600
700
800
900
1000
1100
1200
1300
1400
1500
0 1 2 3 4O (wt%)
Tem
pera
ture
( °C)
Expected influenceof 600 wt ppm H
[H]=
0aZr(O)
bZra+b Zr
51.3 2.0 5.0
a+b Zr expecteda Zr expected
a+b Zr expecteda Zr expected
16th International Symposium on the Zirconium in the Nuclear Industry – Chengdu, China 18/ 22
Testing procedure
time
temperature
steam
1050°C - 5 min
H h
omog
eniz
atio
n+
Zr te
xtur
e re
mov
al
O c
harg
ing
bysa
mpl
e ox
idat
ion
dura
tion
adju
sted
(Cat
h.Pa
w.)
3 temp. tested: 1000, 1100 and 1200 °C
Elec
trol
ytic
al H
Cha
rgin
g at
ED
F
H,O
mea
sure
men
t (H
E)O
mea
sure
men
t by
wei
ght g
ain
O d
isso
lutio
n an
dho
mog
eniz
atio
n
H m
easu
rem
ent (
HE)
Melting pointof ZrO2 too hot
10 hr at 1000°C3h at 1100 and 1200°C
(CEA procedure)
Wat
er q
uenc
h(a
+bZr
sam
ples
onl
y)
Ana
lysi
s pe
rfor
med
[H] and [O] contents are used to check that the vials keep tight during HTsteps
H,O
mea
sure
men
t (H
E)O
mea
sure
men
t by
wei
ght g
ain
Perturbatedby matr’l loss
not reliable
•H,O
mea
sure
men
t(H
E),
•Wei
ght g
ain
(not
acc
urat
e),
•EPM
A m
easu
rem
ents
(hom
ogen
eity
+ d
istr
ibut
ion)
Vacuum(quartz vial)
Vacuum(quartz vial)
16th International Symposium on the Zirconium in the Nuclear Industry – Chengdu, China 19/ 22
Oxide aZr(O) Prior-bZr
0
5
10
15
20
25
-50 0 50 100
Oxy
gen
conc
entr
atio
n (w
t%)
Measured O profile (#26 sample):steam oxidation 60 s at 1200°C
DIFFOX simulation
a/(a+b)
(a+b)/b
Oxide aZr(O) Prior-bZr
0
5
10
15
20
25
-50 0 50 100Distance to metal / oxide interface (mm)
Oxy
gen
conc
entr
atio
n (w
t%)
Measured O profile (#26 sample):steam oxidation 60 s at 1200°C
DIFFOX simulation
a/(a+b)
(a+b)/b
Determination of phase boundaries: After steam oxidation
•Assuming slow diffusion of oxygen at RT, phase boundaries can be derivedfrom EPMA profile after steam oxidation (before homogenization process),•Low accuracy because EPMA measurement is not accurate at the interface•Some improvements are still needed in the DIFFOX code.
time
temperature
steam
1050°C - 5 min3 temp. tested: 1000, 1100 and 1200°C
10 hr at 1000°C3h at 1100 and 1200°C
(CEA procedure)
Wat
er q
uenc
h(a
+bZr
sam
ples
onl
y)
Vacuum(quartz vial)
Vacuum(quartz vial)
16th International Symposium on the Zirconium in the Nuclear Industry – Chengdu, China 20/ 22
Determination of phase boundaries: after homogenization
•At equilibrium: direct measurement of O contents in both aZr(O) and prior bZr•Fe and Cr segregates to the b-phase during HT treatment
9/119/119/11
Distance to the external surface (mm)O c
once
ntra
tion
(wt %
)
Cr
Fe
O
200 µm
Cr
Fe
O
200 µm
0
1
2
3
0 50 100 150 200 250 300
Cr
Fe
O
200 µm
aZr
(O)
prio
r-bZr
Sample # 20
time
temperature
steam
1050°C -5 min3 temp. tested: 1000, 1100 and 1200°C
10 hr at 1000°C3h at 1100 and 1200°C
(CEA procedure)
Wat
er q
uenc
h(a
+bZrs
ampl
es o
nly)
Vacuum(quartz vial)
Vacuum(quartz vial)
16th International Symposium on the Zirconium in the Nuclear Industry – Chengdu, China 21/ 22
Determination of phase boundaries: Results Summary
•The results are consistent with expectations•Some scatter in the data
This work, on oxidizedThis work, on homogenizedErickson ~600 ppmH (1964)Brachet 600 ppm (2001)
a/(a+b)
b/(a+b)
Chung & Kassner, 0 ppm H (1979)
500
600
700
800
900
1000
1100
1200
1300
1400
0 1 2 3 4O concentration (wt%)
T( °
C)
a Zr(O)
b Zr
a+b Zr
16th International Symposium on the Zirconium in the Nuclear Industry – Chengdu, China 22/ 22
Summary•Overall agreement on the key role played by O-distribution during a LOCAtransient•DIFFOX is the IRSN calculation code dedicated to this assessment
•A set of experiments dedicated to the influence of LT oxide layer dissolutionwas performed showing that:
- the LT oxide layer can be both protective or not,- DIFFOX calculations are consistent with a protective layer
•The influence of 600 ppm H on the Zy-O phase diagram was studied and newmodeling data is provided.
•Further studies are required to provide validation data in the duration range of aLOCA (including shorter steam exposure and wider temperature range).
•Detailed influence of hydrogen on Zy-O phase diagram (300 and 1000 wppm)
•Transient oxidation-cooling experiments are planned to increase the validationfield of DIFFOX
Further studies