Development of thermokinetic tools for phase transformation studies of Zr alloys in service and LOCA conditions C. TOFFOLON-MASCLET, L. MARTINELLI, C. DESGRANGES, P. LAFAYE, J.-C. BRACHET, F. LEGENDRE, J.-C. CRIVELLO, J.-M. JOUBERT, D. MONCEAU 18 JUIN 2019 19th International Symposium on Zr in the Nuclear Industry, May 20-23 2019, Manchester, UK
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Development of
thermokinetic tools for phase
transformation studies of Zr
alloys in service and LOCA
conditions
C. TOFFOLON-MASCLET, L. MARTINELLI,
C. DESGRANGES, P. LAFAYE, J.-C. BRACHET,
F. LEGENDRE, J.-C. CRIVELLO, J.-M. JOUBERT,
D. MONCEAU
18 JUIN 2019
19th International Symposium on Zr in the Nuclear Industry, May 20-23 2019, Manchester, UK
BACKGROUND
18 JUIN 2019
| PAGE 219th International Symposium on Zr in the Nuclear Industry, May 20-23 2019, Manchester, UK
As nuclear fluel cladding materials, Zr alloys are subjected to numerous solicitations both in:
service conditions
❑ Pressurized water: 155 bars
❑ Water temperature: 320-360°C
❑ Neutron irradiation
❑ Oxidation / hydriding
LOCA conditions❑ Internal pressure: up to > 100 bars inducing
creep/ballooning and burst
❑ Max (Peak Cladding) Temperature : 1200 °C
❑ Steam environment inducing High Temperature
Oxidation and potential secondary hydriding
The development of thermokinetic tools enables the determination of:
- phase transformation temperatures- phases chemical compositions- phases volume fractions- precipitation of more or less brittle phases- new alloy compositions- …
Considering the influence of microstructure on mechanical properties
OVERVIEW
18 JUIN 2019 | PAGE 319th International Symposium on Zr in the Nuclear Industry, May 20-23 2019, Manchester, UK
New thermodynamicdatabase for Zr alloys
Systematic use of Density Functional Theory (DFT) and Special Quasirandom Structure (SQS)
calculations
Phase diagram and thermodynamic data calculationsExtended to Cr containing alloys for Cr-coatedZr EATF R&D
Numerical code Ekinox-Zr
Simulation of O concentration profiles and thickness evolution of the differentphases appearing/developing during a LOCA transient
Thermodynamic tool Kinetic tool
Linked with Open Calphad/OCASI and thermodynamic database
THERMODYNAMIC TOOL
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| PAGE 4
19th International Symposium on Zr in the
Nuclear Industry, May 20-23 2019, Manchester,
UK
18 JUIN 2019
| PAGE 519th International Symposium on Zr in the Nuclear Industry, May 20-23 2019, Manchester, UK
NEW THERMODYNAMIC DATABASE :
Zr-Cr-Fe-Nb-Sn SYSTEM
Binary and ternary models are combined into a quinary database.
*Barberis et al., 17th Int. Symp. Zr Nucl. Indust, STP1543, Hyderabad, India, 2015
KINETIC TOOL
18 JUIN 2019
| PAGE 14
19th International Symposium on Zr in the
Nuclear Industry, May 20-23 2019, Manchester,
UK
CONTEXT: MICROSTRUCTURAL EVOLUTIONS DURING LOCA HIGH
INFLUENCE ON THE MECHANICAL PROPERTIES: BALLONING & BURST, WATER
QUENCHING AND POST-QUENCHING RESISTANCE/DUCTILITY…)
18 JUIN 2019
| PAGE 1519th International Symposium on Zr in the Nuclear Industry, May 20-23 2019, Manchester, UK
Steam
<900s
Time
Te
mp
era
ture
of th
e c
lad
din
g
at a
giv
en
axia
l p
ositio
n (
°C)
400
800
1200
ANL, ICL#2
JAEA, A 3-1
Example of Large
Break LOCA transient
CEA
Prior-βZr
αZr(O)
ZrO2
Zr
(+ H)
ZrO2
Ex.: Single-side oxidation
Prior-βZr
Zr(O)
ZrO2
Zr + 2H2O → 2H2 + ZrO2
Zr(cc)
Zr (hcp)
ZrO2(tetra.)
αZrO2(mono.)
Zr O
βZr
ZrO2
βZr Zr(O)
ZrO2
αZr(O) βZr
Ste
am
ZrO2
Oxyge
n
co
nte
nt
0.14-0.9 wt.%
1-5 at.%
2-7 wt.%
10-29 at.%
~25 wt.%
~66 at.%
Distance from the outer surface
Loss Of Coolant Accident (LOCA)
CONSEQUENCES OF HIGH TEMPERATURE OXIDATION ON
POST-QUENCH MECHANICAL BEHAVIOR OF THE CLADDING
| PAGE 1619th International Symposium on Zr in the Nuclear Industry, May 20-23 2019, Manchester, UKJ.-C. Brachet et al. Journal of ASTM
international, 5, n°5 (2008), Paper ID JAI101116
[O]
x
C0
Cox/αCα/ox
C β /α
Cα/β
Cox/vap
Ex
tern
al
surf
ace
Ex
tern
al
surf
ace
Brittle Brittle
[O]
x
O
diffusion
profile
O
diffusion
profile
C β /α
0.4 wt%
Brittle Ductile
ZrO2 αZr(O) prior-βZr
eox eα
O
diffusion
profile
O
diffusion
profile
Brittle Ductile
Remaining ductility at RT only in the prior-Zr layerfor [O] < 0.4wt%Otherwise ductile → brittle
Nuclear
fuel
Create a tool able to forecast thicknesses of brittle and ductile phases, O diffusion profiles (and weight gains) as a function of HT steam oxidation time and temperature(and able to take into account the additional effect of hydrogen)
At Room-Temperature (RT):
18 JUIN 2019 | PAGE 1719th International Symposium on Zr in the Nuclear Industry, May 20-23 2019, Manchester, UK
» Chemical species and atomic
defects transport
via atomic solid diffusion
» Interface reaction
local thermodynamic equilibrium
» Intermediate scale• system is described by "slabs" of
constant concentration :
[O] in the metal layers
[VO] in the oxyde phase
1st and 2nd Fick‘s law
» Moving boundaries algorithm for
interfaces motion
» Numerical time integration» growth kinetics
» Diffusion of chemical species
and vacancies concentration profiles
in the oxide scale
in the metal
Initially developped for Ni base alloys
Numerical code EKINOX-Zr
(ESTIMATION KINETICS OxIDATION MODEL FOR ZR-BASED ALLOYS)
Model enables calculation of
NUMERICAL CODE EKINOX-ZR
(ESTIMATION KINETICS OXIDATION MODEL FOR ZR-BASED ALLOYS)
18 JUIN 2019
| PAGE 1819th International Symposium on Zr in the Nuclear Industry, May 20-23 2019, Manchester, UK
Interface
OCASI
𝐶𝛼/𝛽, 𝐶𝛽/𝛼
EKINOX numerical resolution
of diffusion equations
OPENCALPHAD + Zircobase
(thermodynamic calculations)
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| PAGE 1919th International Symposium on Zr in the Nuclear Industry, May 20-23 2019, Manchester, UK
Ekinox-Zr has already demonstrated its ability at:
Simulating O diffusion profiles in Zr(O) and Zr
[1]
Taking into account the influence of H[2]
Taking into account the effectof a pre-oxide layer on the O
concentration profile [3]
During isothermal HT oxidation (1100 < T < 1250°C)
[1] C. Corvalan et al., JNM, 400, 3 (2010) 196-204
[2] B. Mazères et al., Oxid. Met., 79 (2013) 1-2
[3] B. Mazères et al., Corros. Sci., 103 (2016) 10-19
New development: simulation of anisothermal (HT oxidation) transients
18 JUIN 2019
| PAGE 2019th International Symposium on Zr in the Nuclear Industry, May 20-23 2019, Manchester, UK
2°C.min-1 20°C.min-1
Comparison betweencalculated and
experimental (TGA) anisothermal weight
gain variation of Zircaloy-4 upon heating
under O2+He environment
at 2°C/min and 20°C/min
18 JUIN 2019 | PAGE 2119th International Symposium on Zr in the Nuclear Industry, May 20-23 2019, Manchester, UK
Calculated O concentration profiles in Zircaloy-4 alloy for anisothermaloxidation at two different heating rates (2 and 20°C/min) at t = 200s
Similar ECR can be reached by different LOCA type anisothermal transients : the resulting O concentration profiles can potentially be very different
18 JUIN 2019 | PAGE 2219th International Symposium on Zr in the Nuclear Industry, May 20-23 2019, Manchester, UK
CONCLUSIONS
Development of a new thermodynamic database for Zr alloys including systematicand massive use of DFT and SQS calculations
Consistency of the database: very good agreement of thermodynamic computations with experimental data
Improvement of the Ekinox-Zr numerical code: enabling anisothermal calculationsof the HT phase thicknesses and associated oxygen concentration profiles inducedby HT steam oxidation typical of LOCA
Include H and O in the thermodynamic database : « work in progress! »
Ekinox-Zr : - Extend anisothermal calculations from room temperature to high temperature- Adaptation of the code for the simulation of HT oxidation of Cr-coated EATF claddings
FURTHER WORK
Direction de l’Énergie Nucléaire
Département des Matériaux pour le Nucléaire
Service de Recherche de Métallurgie Appliquée
Commissariat à l’énergie atomique et aux énergies alternatives
Centre de Saclay | 91191 Gif-sur-Yvette Cedex
T. +33 (0)1 69 08 21 39
Etablissement public à caractère industriel et commercial | RCS Paris B 775 685 01918 JUIN 2019
19th International Symposium on Zr in the
Nuclear Industry, May 20-23 2019,
Manchester, UK
| PAGE 23
This work is funded by the project GAINE
from the French Nuclear tripartite Institute
CEA – EDF - FRAMATOME
100
(Nb)8:(Fe)16
(Zr)8:(Nb)16
(Nb)8:(Zr)16
(Zr)8:(Fe)16 (Fe)8:(Zr)16
(Zr)8:(Zr)16(Fe)8:(Fe)16
(Nb)8:(Nb)16
(Fe)8:(Fe)16
Structure Intermetallic
compound
Wyckoff
positionSpace
group
C15 ZrFe28a (Zr)
16d (Fe)
Fd-3m
(227)
22 = 4 end-members for a binary system
32 = 9 end-members for a ternary system
C36
site 8a0
site
16d
(Zr)8:(Fe)16
(Fe)8:(Zr)16
WHY SYSTEMATIC USE OF DFT AND SQS CALCULATIONS ? → SUBLATTICE MODEL
(Zr)8:(Fe)16 (Fe)8:(Zr)16(Fe)8:(Fe)16(Zr)8:(Zr)16
(Fe)8:(Nb)16
ICMPE | 27 OCTOBRE 2017| PAGE 7
(Zr)8:(Fe,Zr)16
(Fe,Zr)8:(Fe)16
(Zr)8:(Zr)16
100
MODÈLE EN SOUS-RÉSEAUX
Phase Groupe
d’espace
Wyckoff (CN) Configurations Système Nombre de
sous-
réseaux
Modèle en sous-réseaux
C15 Fd-3m (227) 8a (16);
16d (12)
25 Système
quinaire
2 (Cr,Nb,Fe,Sn,Zr)1
(Cr,Nb,Fe,Sn,Zr)2
C14 P63/mmc
(194)
2a (12);
4f (16);
6h (12)
125 Système
quinaire
3 (Cr,Nb,Fe,Sn,Zr)2
(Cr,Nb,Fe,Sn,Zr)4
(Cr,Nb,Fe,Sn,Zr)6
C36 P63/mmc
(194)
4e (16);
4f (16);
4f (12); 6g (12); 6h (12)
125 Système
quinaire
3 (Cr,Nb,Fe,Sn,Zr)4
(Cr,Nb,Fe,Sn,Zr)4
(Cr,Nb,Fe,Sn,Zr)16
C15 C14 C36
ICMPE | 27 OCTOBRE 2017| PAGE 8
MODÈLE EN SOUS-RÉSEAUX
Phase Groupe
d’espace
Wyckoff (CN) Prototype Système Nbre de
sous-
réseaux
Modèle en sous-réseaux
C15 Fd-3m (227) 8a (16);
16d (12)
MgCu2 Système
quinaire
2 (Cr,Nb,Fe,Sn,Zr)1
(Cr,Nb,Fe,Sn,Zr)2
C14 P63/mmc
(194)
2a (12);
4f (16);
6h (12)
MgZn2 Système
quinaire
3 (Cr,Nb,Fe,Sn,Zr)4
(Cr,Nb,Fe,Sn,Zr)2
(Cr,Nb,Fe,Sn,Zr)6
C36 P63/mmc
(194)
4e (16);
4f (16);
4f (12); 6g (12); 6h (12)
MgNi2 Système
quinaire
3 (Cr,Nb,Fe,Sn,Zr)4
(Cr,Nb,Fe,Sn,Zr)4
(Cr,Nb,Fe,Sn,Zr)16
μ* R-3m (166) 3a (12) ;
6c (15); 6c (16);
6c (14);
18h (12)
W6Fe7 Cr-Fe-Nb 4 (Cr,Fe,Nb)1
(Nb)4
(Cr,Fe,Nb)2
(Cr,Fe,Nb)6
σ* P42/mnm
(136)
2a (12); 8i (12);
4f (15); 8i (14); 8j (14)
Cr0.49Fe0.51 Cr-Fe-Nb 2 (Cr,Fe,Nb)1
(Cr,Fe,Nb)2
* J.-M. Joubert et al. “Mixed site occupancies in the μ phase” Intermetallics 12 (2004) 1373–1380
* J.M. Joubert, “Crystal chemistry and Calphad modeling of the σ phase”, Prog. Mater. Sci. 53 (2008)
528–583.
ICMPE | 27 OCTOBRE 2017| PAGE 9
18/06/2019
TECHNIQUES DE CALCULS
ICMPE | 27 OCTOBRE 2017| PAGE 9
Calculs DFT-SQS des ΔHm
Calculs DFT des ΔHf
C15 C14 C36
0 20 40 60 80 1000
2
4
6
8
10
12
Cr-Fe system
SQS-ferromagnetic
SQS-parramagnetic
experiments
H
mix (
kJ/m
ol. a
t.)
Composition (at. % Fe)
Consistance de la description !Solutions solides peu étendues
0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0
500
750
1000
1250
1500
1750
2000
2250 [STE61]
[PRE69]
[DAR69]
This work
SnCr XSn
NUMERICAL CODE EKINOX-Zr
(ESTIMATION KINETICS OXIDATION MODEL FOR ZR-BASED ALLOYS)
18 JUIN 2019
| PAGE 2819th International Symposium on Zr in the Nuclear Industry, May 20-23 2019, Manchester, UK
Interfaces conditions : 1st and 2nd Fick’s law :
Moving interfaces O flux at the different interfaces :
OpenCalphad
/OCASI +
Zircobase
18 JUIN 2019 | PAGE 2919th International Symposium on Zr in the Nuclear Industry, May 20-23 2019, Manchester, UK