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1 FR09, Kyoto, 7-11 December 2009
Performance Evaluation of Metallic Fuel for SFR
International Conference on Fast Reactors and Related Fuel Cycles (FR09), Kyoto, Japan
9 December 2009
Byoung Oon LEE
2 FR09, Kyoto, 7-11 December 2009
Outline
IntroductionIDiffusion Couple Test IIIrradiation TestIIIModelingIVMetal Fuel DesignVSummaryVI
3 FR09, Kyoto, 7-11 December 2009
IntroductionI
4 FR09, Kyoto, 7-11 December 2009
Introduction� Metal fuel development project for SFR in Korea
– U-TRU-Zr metallic fuel– Cladding material : FMS� The performance analysis is essential to assure an
adequate fuel performance and its integrity� The present study represents progress results of evaluating
the performance of metal fuel for SFR in Korea ’07 ’10 ’15 ’20 ’25 ’28
Metal Fuel AssemblyFab. (U-X-Zr)
Fuel Fab. In Hot Cell(U-TRU-Zr)
Fuel Fab. Facility Operation(U-TRU-Zr)
Fuel Fab. for Demo. SFR(U-TRU-Zr)
Metal Fuel RodFab. (U-X-Zr)Fuel
Develop.
Fuel Perform.
Eval.Fuel Rod Irradiation in Fast Reactor (Abroad)
Fuel irradiation in HANARO
Verification Irradiation of Fuel Assembly (Abroad)Transient Tests in Hot Cell Transient Behavior Tests in Reactor (Abroad)
Fuel Design, Fuel Performance Modeling, and Computer Code Development
Control Rod Assembly Development
5 FR09, Kyoto, 7-11 December 2009
Diffusion CoupleDiffusion CoupleDiffusion CoupleDiffusion Couple
TestsTestsTestsTestsIrradiation TestIrradiation TestIrradiation TestIrradiation Test
ModelingModelingModelingModeling
Fuel Performance Evaluation
�Verification of Fuel PerformanceVerification of Fuel PerformanceVerification of Fuel PerformanceVerification of Fuel Performance
�Design and fabrication of Design and fabrication of Design and fabrication of Design and fabrication of
Irradiation Capsule in HANAROIrradiation Capsule in HANAROIrradiation Capsule in HANAROIrradiation Capsule in HANARO
�Diffusion couple test between Diffusion couple test between Diffusion couple test between Diffusion couple test between
metal fuel and cladding metal fuel and cladding metal fuel and cladding metal fuel and cladding
� UUUU----ZrZrZrZr----X vs. HT9 or T91 or X vs. HT9 or T91 or X vs. HT9 or T91 or X vs. HT9 or T91 or
Barrier claddingBarrier claddingBarrier claddingBarrier cladding
�Thermal Conductivity Thermal Conductivity Thermal Conductivity Thermal Conductivity
�FGRFGRFGRFGR
�Fuel constituent migrationFuel constituent migrationFuel constituent migrationFuel constituent migration
�Deformation etcDeformation etcDeformation etcDeformation etc
Metal Metal Metal Metal Fuel Fuel Fuel Fuel
Performance Performance Performance Performance
EvaluationEvaluationEvaluationEvaluation
10
15
20
25
30
35
40
0 100 200 300 400 500 600 700 800Temperature, °C
Therm
al co
nduc
tivity
, W/m
-K
U-10Zr(measured)U-Zr-Ce(measured)U-10Zr[Bill one]U-10Zr[Takahashi]U-Zr-Ce(evaluated)
10
15
20
25
30
35
40
0 100 200 300 400 500 600 700 800Temperature, °C
Therm
al co
nduc
tivity
, W/m
-K
U-10Zr(measured)U-Zr-Ce(measured)U-10Zr[Bill one]U-10Zr[Takahashi]U-Zr-Ce(evaluated)
T91 V U-10Zr-4CeT91 V U-10Zr-4Ce
FMFMFMFM
SSSS
Cr
Cr
Cr
Cr22 22OO OO
33 33
UUUU----
10Zr10Zr10Zr10Zr
FMFMFMFM
SSSS
Cr
Cr
Cr
Cr22 22OO OO
33 33
UUUU----
10Zr10Zr10Zr10Zr
Fuel Design Fuel Design Fuel Design Fuel Design
�Evaluation of Design Limit by Evaluation of Design Limit by Evaluation of Design Limit by Evaluation of Design Limit by
MACSIS etcMACSIS etcMACSIS etcMACSIS etc
�Fuel Spec for High Fuel Spec for High Fuel Spec for High Fuel Spec for High burnupburnupburnupburnup and and and and
high temperature operation high temperature operation high temperature operation high temperature operation
0.0000
0.0005
0.0010
0.0015
0 2 4 6 8 10 12 14
Burnup (at%)
CDF
Inner fuel, Mod. HT9,1.75 plenum
middle fuel, Mod. HT9,1.75 plenum
outer fuel, Mod. HT9,1.75 plenum
middle fuel, Mod. HT9, 2.0 plenum
outer fuel, Mod. HT9,2.0 plenum
CDF limit
6 FR09, Kyoto, 7-11 December 2009
Metal Fuel Configuration
7 FR09, Kyoto, 7-11 December 2009
Diffusion Couple Test II
I.1 Diffusion couple tests without barrierI.2 Diffusion couple tests with a metallic foil
barrierI.3 Diffusion couple test with a surface
treatment
8 FR09, Kyoto, 7-11 December 2009
II.1 Diffusion couple tests without barrier�Diffusion couple tests of U-Zr-(0, 2)Ce with FMS (700℃℃℃℃)
– Various interaction phases– Major phase : UFe2, U6Fe, and ZrFe2– Similar results of US and JAPAN
� Diffusion couple tests of U-Zr-(0, 2)Ce with FMS (740℃℃℃℃)
– Thickness of the interaction region : different from Keiser’s observation
• microstructures were similar – Gray phase of UFe2, dark one of Zrrich-line layer, and mixed phase with U and Zr were observed
U–10Zr vs. HT9 (740℃℃℃℃, 96 h)
U–10Zr vs. HT9 (700 ℃℃℃℃, 96 h)
HT9 U-10Zr
Zr richUFe2
(U,Zr) phase
9 FR09, Kyoto, 7-11 December 2009
II.1 Diffusion couple tests without barrier� U-10Zr and HT9 (800℃, 25h)
–SEM revealed that the clad lost about 250㎛ of its thickness–From the EDX
• U, Fe and Cr diffused into each other at the opposite direction �U-Zr-Fe-Cr compound as U6(Fe,Cr), Zr(Fe,Cr)2, and U(Fe,Cr)2
Fuel CladInterface
Diffusion of Fe, Cr
Diffusion of U, Zr
Fuel CladInterface
Diffusion of Fe, Cr
Diffusion of U, Zr
U–10Zr vs. HT9 (800℃℃℃℃, 25 h)
10 FR09, Kyoto, 7-11 December 2009
II.2 Diffusion couple tests with a metallic foil barrier
� Diffusion couple tests of U-Zr-(0, 2)Ce were carried out for the barrier foils –Zr, Mo, Nb, Ti, Ta, V, and Cr
� Zr–dissolved into the matrix – its thickness was significantly reduced � Mo
–part of the Mo element reacted with the U-10Zr fuel� Nb, Ti
–barrier elements and the fuel diffused into each other so that the reaction layer was formed.
� Ta–EDX analysis revealed that Ta reacted with the fuel, where it diffused into the fuel component.
11 FR09, Kyoto, 7-11 December 2009
II.2 Diffusion couple tests with a metallic foil barrier� V
– no reaction between the barrier material and the fuel component• Inter-diffusion was completely prevented
– EDX analysis revealed that there was no U in the V layer.
– V–Fe–Zr layer was observed between the V foils and the FMS • measured composition : 93.5 at.%V–4 at.%Fe–2.5 at.%Zr.
• Reduction of V foil thickness� Cr
– Neither inter-diffusion nor eutectic reaction
� V and Cr exhibited the most promising performance
U–10Zr and HT9 with a V barrier foil (800℃℃℃℃, 25 h)
Zr
V
93.5V-4Fe-2.5Zr
HT9 U-10ZrV
Summary of the metallic foil barrier performance
NoNoYesCrNoNoYesVYesNoYesTaYesNoYesMoYesYesYesTiYesYesYesNbYesYesYesZr
Reaction with fuel
Element Interdiffusion
Eutectic melting preventionElement
12 FR09, Kyoto, 7-11 December 2009
II.3 Diffusion couple test with a surface treatment�Final application of a barrier
cladding requires the barrier in the surface of a cladding tube –Electroplating (for Cr) and vapor deposition (for Zr and V)
�Cr barrier electroplated on FMS–Cr prevented the eutectic melting between U-10Zr and HT9 at 700, 740, and 800 ℃℃℃℃. –Fuel constituent such as U have penetrated locally along the crack in the barrier
• uranium compound along the clad surface
U-10Zr and HT9 with the electroplating of Cr after the
diffusion couple test (800℃℃℃℃, 25 h)
� It seems that a crack affects the fuel-cladding interaction in a negative way– further analysis will be carried out to investigate the exact phenomenon
13 FR09, Kyoto, 7-11 December 2009
II.3 Diffusion couple test with a surface treatment�Zr-vapor-deposited barrier
–no visible phase formation –excellent barrier performance, contrary to the case of the Zrmetallic foil– further analysis will be continuously carried out
�V-vapor-deposited barrier–not effectively prevent inter-diffusion contrary to the V foil– It seems that the thickness of V (~1.3 μμμμm) was too thin –Diffusion couple test will be carried out with thick barrier cladding
U-10Zr vs. HT9 with the Zr vapor deposition (800℃℃℃℃, 25 h)
ZrZr
ZrCr
Fe
V
Zr Cr Fe
Fe
Cr
U-10Zr vs. HT9 with the V vapor deposition (800℃℃℃℃, 25 h)
14 FR09, Kyoto, 7-11 December 2009
Irradiation TestIII
15 FR09, Kyoto, 7-11 December 2009
Fuel irradiation test � Schedule
– 2010 : irradiation in HANARO– 2008-2009 : irradiation capsule design and fabrication
� Objectives – Identify the Ce-bearing fuel performance and the characteristics of barrier cladding
� Irradiation condition– Fuel : U-10Zr and U-10Zr-6Ce– Cladding : FMS– Maximum burnup : 3 at% (1st HANARO irradiation test) – Linear power : 306 W/cm, – Expected duration : ~150 EFPD
� Fast reactor condition – Thermal neutron flux filter : Hf or Boral plate– Fuel temp. control : He gap– Fuel/cladding gap bonding :Na
Fuel
Na
Outer tube
Gap (He, 60µm)
Coolant
Cladding
Fuel Slug Cross Section
Upper Part
Na
Fuel Slug Cross Section
Upper Part
Na
16 FR09, Kyoto, 7-11 December 2009
Irradiation capsule � Capsule design
– Two test sections• each section accommodates six
rodlets– The fuel rod is contained in the
sealing tube for safety in case of sodium leakage from the cladding
Mid-core
bottom top
Mid-core
bottom top
flux
Lower partUpper part
Irradiation capsule dimension
5.628.624.65.515.83.7
Fuel Cladding Outer tube Dia. (mm) Density (g/cm3) Outer dia.(mm) Inner dia.(mm) Outer dia.(mm) Inner dia.(mm)
17 FR09, Kyoto, 7-11 December 2009
ModelingIV
IV.1 Thermal conductivity modelIV.2 Fuel constituent migration model
18 FR09, Kyoto, 7-11 December 2009
MACSIS CODE
INPUT Geometry, Power History, Model Specifications
Calculate Initial Conditions
Power, Burnup, Fluence
Coolant Temperature
Cladding Temperature
Cladding Deformation
Fuel/Clad HTC
Fuel Temperature
Constituent Redistribution
Fuel Swelling
Fission Gas Release
Plenum Pressure
Failure Probability
OUTPUT
Is time ended?
No
F/C Gap Converge?
No
Yes
Yes
STOP
� Main structure� Fuel temp. calculation routine� FGR calculation routine� Cladding deformation calculation routine
� Main Function� Axial and radial temperature distribution� Fission gas release including He release� Fuel constituent migration� Cladding deformation by plenum pressure� Cumulative damage fraction (CDF) � Probabilistic estimation of CDF
in connection with Weibull analysis � Cladding wastage effect by eutectic melting� FCMI by solid fission product
� MA (+ RE) bearing metal fuel behaviormodel is now developing
MACSIS Flow Chart
19 FR09, Kyoto, 7-11 December 2009
IV.1 Thermal conductivity model�RE is precipitated in the U-Zrmatrix
– cause a variation of fuel properties �The effect of the Ce precipitates on effective thermal conductivity is evaluated
– based on models for heterogeneous materials such as Maxwell and Bruggeman models
�Thermal conductivity of the U-Zralloy is reduced
– with an increasing Ce content�Addition of Ce up to 6 wt%
– reduce the thermal conductivity of the U-Zr alloy by less than 5%.
• low volume fraction of the Ce phase• relatively high thermal conductivity of Ce
Effect of the Ce content on the thermal conductivity of U-10Zr
0.95
0.96
0.97
0.98
0.99
1.00
0 200 400 600 800Temperature, °C
kU-10Z
r-Ce /k
U-10
Zr
2Ce
4Ce
6Ce
20 FR09, Kyoto, 7-11 December 2009
IV.1 Measured thermal conductivity �The measured thermal conductivity of the U-Zr-Ce alloy
– by the product of the thermal diffusivity, density, and specific heat
• Thermal diffusivity : laser flash method
• Density : immersion technique• specific heat : Kopp-Neumann’s law
�Thermal conductivity of U-Zr lies in between the Billone or Takahashi’s evaluation
– The effect of Ce on the thermal conductivity of U-Zr alloy is well described by the present heterogeneous mixture models
Comparison of the thermal conductivities for U-Zr-Ce alloys
10
15
20
25
30
35
40
0 100 200 300 400 500 600 700 800Temperature, °C
Therm
al co
nduc
tivity
, W/m
-K
U-10Zr(measured)U-Zr-Ce(measured)U-10Zr[Billone]U-10Zr[Takahashi]U-Zr-Ce(evaluated)
21 FR09, Kyoto, 7-11 December 2009
IV.2 Fuel constituent migration model�U-Pu-Zr Migration
– Based on the Ishida’s model and Hofman’s theory – Reconstruct the quasi-binary U-Zrphase diagram by Ishida’s Concept– Assumption of the diffusion coefficient by Hofman’s theory�Am migration model for U-TRU-Zr
– by using the U-Pu-Zr migration model �The radial profile of Zrredistribution
– The main reason for the migration is the radial solubility change of Zr– The heat of transport also plays an important role in the migration– depletion of Zr in the middle zone was simulated – value of the heat of transport : more than -100,000kJ/mole.
Radial distribution profile of Zr
0
0.1
0.2
0.3
0.4
0.5
0.6
0 0.2 0.4 0.6 0.8 1
Slug Radis (R/R0)
Zr A
tom
Fra
ctio
n
EBR-II data by Ishida EBR-II data by Ishida EBR-II data by Ishida EBR-II data by Ishida initial Zr concentrationinitial Zr concentrationinitial Zr concentrationinitial Zr concentration
calculated value (Q=-100000)calculated value (Q=-100000)calculated value (Q=-100000)calculated value (Q=-100000)507-694 range507-694 range507-694 range507-694 range542-671 range542-671 range542-671 range542-671 range
initial Am concentrationinitial Am concentrationinitial Am concentrationinitial Am concentration
22 FR09, Kyoto, 7-11 December 2009
IV.2 Am migration �Am migration
– calculated by using the MACSIS code and the X501 data
�The migration behavior of Am is similar to that of Zr
– -100,000kJ/mole of the heat of transport was also used
�Simulated Am migration for the X501 fuel
– Am migration along with the migration of Zr was simulated
– At around 700℃℃℃℃ of the fuel centerline temperature, the model predicted that the Am fraction in the fuel center reaches its peak
– There were no centerline Am depletions expected in all range of temperature
Radial distribution profile of Am
0
0.1
0.2
0 0.2 0.4 0.6 0.8 1
Slug Radis (R/R0)
Am
Ato
m F
ract
ion
initial Am concentrationinitial Am concentrationinitial Am concentrationinitial Am concentration
518-722 range (AM)518-722 range (AM)518-722 range (AM)518-722 range (AM)
495-685 range (AM)495-685 range (AM)495-685 range (AM)495-685 range (AM)
463-628 range (AM)463-628 range (AM)463-628 range (AM)463-628 range (AM)
23 FR09, Kyoto, 7-11 December 2009
Metal Fuel DesignV
24 FR09, Kyoto, 7-11 December 2009
Design Criteria � No Fuel Melting
–Fuel Temperature ≤ solidus temperature� No Eutectic Melting
–No eutectic liquifaction• Fuel Surface Temperature (TRU% < 19wt%) ≤ 700 ℃• Fuel Surface Temperature (TRU% ≥19wt%) ≤ 650 ℃
� Cladding Limit–Strain limit criteria
• Thermal creep strain : 1%• Total strain : 3%• Swelling : 5%
–Cumulative Damage Fraction (CDF) limit criteria • Steady state operation : 0.001• Transient operation : 0.2
25 FR09, Kyoto, 7-11 December 2009
Key design parameters
868940Fuel Slug Length (mm)2.251.75Plenum-to-fuel ratio
1.00/0.72/0.59Cladding Thickness (mm)- Inner/middle/outer
7.09.0Pin Outer Diameter (mm)Mod.HT9Mod.HT9Cladding Material
7575Smeared Density (%)
U-30TRU-ZrU-12.6Pu-0.5Am-0.09Cm-0.06Np-10ZrFuel Slug Contents (wt%)
Preliminary case 1 of SFR conceptual design
KALIMER-600 (case 1 core)
26 FR09, Kyoto, 7-11 December 2009
CDF Limit Analysis for KALIMER-600�HT9
– CDF > 0.001 – when the cladding temperature becomes higher than 625 ℃℃℃℃
�Mod.HT9– CDF > 0.001 – when the cladding temperature becomes higher than 645 ℃℃℃℃.
�625 and 645 ℃℃℃℃ are selected as the peak clad temperature
– for the HT9 clad and the Mod.HT9 clad for the Case-1 core, respectively.
CDF as a function of operating temperature for KALIMER-600
(Case-1 core)
1.E-06
1.E-05
1.E-04
1.E-03
1.E-02
1.E-01
1.E+00
580 600 620 640 660 680
Temperature(oC)
CDF
HT9
Mod.HT9
CDF design limit
27 FR09, Kyoto, 7-11 December 2009
CDF LIMITS FOR SFR Preliminary design�CDF <0.001
– Cladding temperature :650℃℃℃℃– P/F ratio : 2– R/th ratio : 5.5
� If the P/F ration was enlarged to 2.25
– R/th ratio needed to satisfy the CDF limit : 6
� If the plenum-to-fuel ratio was enlarged– It was expected that the Mod.HT9 cladding satisfied the CDF limit at the discharge burnup goal
�Sensitivity analysis according to the design parameter will be performed continuously
CDF according to the cladding temperature, P/F ratio, and R/th ratio
0.0000
0.0010
0.0020
0.0030
0.0040
0.0050
0 2 4 6 8Radius/thickness ratio
CDF
temp 650C, P/F=2temp 650C, P/F=2temp 650C, P/F=2temp 650C, P/F=2temp 650C, P/F=2.25temp 650C, P/F=2.25temp 650C, P/F=2.25temp 650C, P/F=2.25temp 610C, P/F=2temp 610C, P/F=2temp 610C, P/F=2temp 610C, P/F=2
28 FR09, Kyoto, 7-11 December 2009
SummaryVI
29 FR09, Kyoto, 7-11 December 2009
Summary� Sodium-cooled fast reactor(SFR) is being developed in
combination with the pyro-processing of spent fuel–U-TRU-Zr metallic fuel is a reference fuel for SFR � Fuel performance evaluation is being performed in the
following tasks; – fuel-cladding diffusion couple tests– fuel irradiation test– performance analysis model development– fuel design � This work forms the basis for establishing key technology
that will evaluate the performance of U-TRU-Zr metallic fuel.