advanced materials for fusion technologyadvanced materials for fusion technology s.j. zinkle1 and a....
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Advanced Materials for FusionTechnology
S.J. Zinkle1 and A. Kohyama2
1Oak Ridge National Laboratory, Oak Ridge, TN USA 2Institute of Advanced Energy, Kyoto University, Kyoto, Japan
19th IEEE/NPSS Symposium on Fusion Energy
January 22-25, 2002
Atlantic City, New Jersey, USA
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OUTLINE
• Development of Improved Materials–Advanced steels, including Nanocomposited ferritic steel–Refractory alloys (V, Mo, W alloys)–New welding technology–Ceramic composites
• Brief comments on prospects for improved Cu alloysand nonstructural materials
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INTRODUCTION
• Major design criteria for structural alloys include–Resistance to He embrittlement & swelling from (n,α) reactions
–high temperature strength–low temperature radiation embrittlement resistance–Safety and environmental (disposal) issues
• Major design criteria for ceramic composites include–Thermal conductivity degradation–Reduced-cost fabrication and joining techniques–Safety and environmental (disposal) issues
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Low uniform elongations occur in many BCC and FCCmetals after low-dose irradiation at low temperature
Uniform elongation of neutron-irradiated V-4Cr-4Ti
-2
0
2
4
6
8
10
12
0 100 200 300 400 500 600 700
Un
ifo
rm E
lon
gat
ion
(%
)
Test Temperature (˚C)
0.5 dpa
0.1 dpa
Test Temperature isIrradiation Temperature
0
2
4
6
8
10
0.0001 0.001 0.01 0.1 1 10
Fabritsiev et al (1996)Heinisch et al (1992)Singh et al. (1995)
Uni
form
Elo
ngat
ion
(%)
Damage Level (dpa)
Unirradiatedelongations
Tirr
=36-90˚C
Uniform elongation of neutron-irradiated GlidCop Al25 and CuCrZr
0
5
10
15
20
25
30
0 50 100 150 200 250 300 350 400
Uni
form
Elo
ngat
ion
(%)
Irradiation and Test Temperature (˚C)
CuCrZr
ODS Cu
GlidCop Al25
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0
100
200
300
400
500
600
700
0 0.05 0.1 0.15 0.2 0.25 0.3
Load-Elongation Curves for V-4Cr-4Ti Irradiated in HFBR to 0.5 dpa
Eng
inee
ring
Stre
ss, M
Pa
Normalized Crosshead Displacement, mm/mm
110˚C 270˚C
325˚C
420˚C
Tt e s t
~Tirr
100 nm100 nm
TTtesttest==TTirrirr=270=270 ˚̊CCg=011
g=011
Irradiated Materials Suffer Plastic Instabilitydue to Dislocation Channeling
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Radiation-induced Tensile "Embrittlement" does notNecessarily Produce Fracture Toughness Embrittlement
0
5
10
15
20
0
50
100
150
200
0 50 100 150 200 250 300 350 400
Un
ifo
rm e
lon
gat
ion
(%
)
Fra
ctu
re T
ou
gh
nes
s K
JQ (
MP
a-m
1/2)
Test Temperature (˚C)
CuCrZr, 0.3 dpaTähtinen et al 1998
eU,
irradiated
eU, unirr.
KJ Q
, unirr.
KJ Q
, irradiated
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Application of Thermal Defect Resistance Modelto Predict Conductivity of Irradiated SiC
0
0.02
0.04
0.06
0.08
0.1
0.001 0.01 0.1 1
Ad
ded
Th
erm
al D
efec
t R
esis
tan
ce
dpa
690-720 °C
240-270 °C
490-510 °C
TRIST-TC1
Estimated Thermal Conductivity : CVD SiC
1/Krd @t=0 (m-K/W)0.014240-270°C0.008490-510°C0.002690-720°C
( m - W / K )
• Maximum irradiated thermal conductivity for SiC is estimated to be ~ 10 W/m-K at 500°C, ~37 W/m-K at 700°C
0
50
100
150
200
250
300
350
0 200 400 600 800 1000 1200
K (
W/m
-K)
Temperature (C)
Saturation Conductivity for Morton CVD SiC
unirradiatedhigh conductivity
Kirr(T) : W/m-K1/Krd sat.(m-K/W)1 3.07240-270°C1 0.09490-510°C3 7.018690-720°C
1 / Krd
model
1K (T)
1K (T)
1K (T)irr unirr rd
= +
K TK T K T K Ku gb d rd
( )( ) ( )
[ ] = + + +
−1
0
1 1 1 1
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0 200 400 600 800 1000 1200 1400
SiC/SiC
CuNiBe
316 SS
F/M steel
ODS ferritic st.
V-4Cr-4Ti
Nb-1Zr-.1C
Ta-8W-2Hf
Mo (TZM)
W
Temperature (˚C)
Current Alloy Systems Have Key Limitations• V-4Cr-4Ti Alloy
- Thermal creep limits- low temperature radiation
hardening- possible He embrittlement- requires MHD coating- poor oxidation resistance
• Ferritic/Martensitic Steels- low temperature radiation
hardening- Thermal creep limits- possible He embrittlement
• Refractory Alloys
Operating Temperature Windows
S.J. Zinkle and N.M. Ghoniem (2000)
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Key Feasibility Issues for Ferritic Steels• Verify ferromagnetic structures are acceptable for MFE• Expand low temperature operating limit (experiments and physical
modeling, master curve methodology)– Development of alloys with improved resistance to low
temperature (<350˚C) embrittlement• Expand high-temperature and dose limits
– Alloy development, including dispersion strengthened alloys– Effect of He on creep rupture
• Resolve system-specific compatibility issues (T barrier development,etc.)
IEA-integrated worldwide ferritic steel program is examining items2 &3 (items 1&4 are being addressed by JA and EU programs)
Note: reduced-activation grades of Fe-9Cr ferritic/martensitic steels(e.g., F82H) have been developed with superior properties compared tocommercial steels (e.g., HT9)
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Void Swelling of Ferritic Steels is Low up to~100 dpa (~10 MW-yr/m2), Although Further
Work is Needed to Examine He Effects
F82H (36 appm He) 10B-doped F82H (330 appm He)
HFIR irradiation at 400˚C to 51 dpa
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Potential New Ferritic/Martensitic Alloy• Dispersion-Strengthened Fe-9.5Cr-3Co-1Ni-0.6Mo-0.3Ti-0.07C steel
– High number density of nano-size TiCprecipitates
• Superior elevated-temperature strengthand impact properties compared toconventional 9-12Cr steels
• Advantage over ODS steels: producedby conventional steel processingtechniques
• Present composition not for nuclearapplications; processing techniqueapplicable to reduced-activationcompositions
Klueh and Buck, J. Nucl. Mater. 283-287 (2000)
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• Perspective• +50 year history
• Benefits• any desired combination of matrix
composition and dispersoid• significant improvements in high
temperature mechanical properties
• Problems• time-consuming & expensive• often produces materials with:
- anisotropic properties- coarse particles with non-uniform size
and spatial distribution
• joining and fabrication• lack of understanding - experiment,
theory, and modeling
Oxide Dispersion Strengthening ApproachFe-13Cr-3W-0.4Ti + 0.25Y2O3
Fe-9Cr-2W + 0.33TiO2 + 0.67Y2O3
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Comparison of Tensile strength of New 12YWTNanocomposited Ferritic Steel vs. other ODS steels
0
200
400
600
800
1000
1200
400 600 800 1000 1200
Temperature K
12YWT
MA956
ODS (SUMITOMO)
9Cr-2WVTa
ODS(ZrO2)
ODS(TiO2)
ODS(MgO)ODS(Al
2O
3)
Str
es
s/M
Pa
Yield strength
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Recently Developed Isotropic Oxide DispersionStrengthened Steels Offer Potential for Improved
Performance
• Thermal creep temperature limit for martensitic Fe-8Cr steel is ~550˚C (vs. >700˚Cfor several grades of ODS steel, including Kobe Fe-12Cr-3W-0.4Ti-0.25Y2O3)
0
50
100
150
200
250
300
350
10 100 1000 104 105
App
lied
Str
ess
(MP
a)
Rupture time (h)
650˚C
F82H(martensitic Fe-8Cr)
ODS Fe-11.5Cr(recrystallized ferrite)
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0
50
100
150
200
250
300
350
400
450
22000 24000 26000 28000 30000 32000 34000 36000
12YWT9Cr-WMoVNb Steel12YMA957 (INCO)
LMP T(25+logt), (K-h)
Str
ess
(MP
a)
700°C, 530h, Stop
800°C, 931h, Stop
900°C, 1104h
800°C, 817h
650°C, 13000h
600°C, 17000h
650°C, 1080h, Rupt.
0
2
4
6
8
10
0 5,000 10,000 15,000
Str
ain
(%)
Time (h)
Nanocomposited 12YWT Ferritic Steel ExhibitsExcellent High Temperature Creep Strength
• Time to failure is increased by several orders of magnitude• Potential for increasing the upper operating temperature of iron
based alloys by ~200°C
800°C and 138 MPa- minimum creep rate
2.13 x 10-10s-1
- total strain2.03%
14,235h
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Atom Probe Reveals the Presence of Nanoclustersin the Mechanically Alloyed 12YWT Ferritic Alloy
• Nano-size clusters– Average composition (at.%) :
O - 23.6 ± 10.6Ti - 19.9 ± 8.7Y - 9.2 ± 7.8
– Size : rg = 2.0 ± 0.8 nm– Number Density : nv = 1.4 x 1024/m3
• Original ~30 nm Y2O3 particles evolveto (Y,Ti,O) enriched nanoclusters
• Nanoclusters not present in ODS Fe-13Cr + 0.25Y2O3 alloy
Isocompositional Surface3-DAP Atomic Coordinates
Y Ti OCr
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0
10
20
30
40
50
60
Cu-Ni-Be T-111 Nb-1Zr TZM V-4Cr-4Ti F82H F/M SiC/SiC
σU
TSK
th(1
- ν)/α
E
(kW
/m)
Ta-8W(1000˚C)
(800˚C) (600˚C) (800˚C)(200˚C)solutionized
& aged
steel(400˚C)
Mo-.5Ti-.1Zr(1000˚C)
q" crit =M (σth/σUTS)
∆x
Refractory Alloys
• Attractive Thermal/Physical Properties– high temperature capabilities
– thermal stress figure of merit
– liquid metal compatibility (Li)
0
20
40
60
80
100
0 500 1000 1500 2000
Podrezov et al 1987, 80%CWITER DDD 1998, as wroughtITER DDD 1998, rexl'dMarschall&Holden 1966, LT wrt+str.reliefMarschall&Holden 1966, LT rexl'dMutoh et al 1995, sintered Gumbsch et al 1998, single XtalBabak&Uskov 1984, powder met.
KQ
(M
Pa-
m1/
2 )
Temperature (˚C)
KC
• Main problems– low fracture toughness– low oxidation resistance– poor mechanical properties
of weldments
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Recent research offers promise for developingrefractory alloys with improved ductility
• Controlled (50-1600 appm) additions of Zr, B, C to molybdenumincreases room temperature ductility of weldments from nearly zeroto etot~20% (M.K.Miller and A.J.Bryhan, 2001)
• Mechanically alloyed W-0.3wt%Ti-0.05wt%C (H. Kurishita et al.,ICFRM-10, Baden-Baden, Oct. 2001)– Avoid (W,Ti)2C brittle phase by limiting max concentration of carbon– Small grain size (~2 µm) helps to dilute harmful oxygen grain boundary
segregation– TiC dispersed particles provide increased toughness (appropriate fracture
mechanics tests needed to verify preliminary smooth bend bar results)
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HAZ HAZWeldFracture occurred predominantly in
the heat affected zones
The fracture mode wastransgranular cleavagewith only small regionsof intergranular fracture.This contrasts theintergranular fracturetypically found incommercial Mo welds.
ALLOY COMPOSITION Zr 1600 appm C 96 appm B 53 appm O 250 appm N 178 appm Mo balance
MECHANICAL PROPERTIES Strain rate: 8.3x10-4 s-1
Mo- 30% Re filler
Ductility 19.5%Yield Stress 481 MPaUTS 544 MPa
Commercial Mo weld: 3% Ductility
Research performed byM. K. Miller, Oak Ridge National Laboratoryand A. J. Bryhan, Applied Materials
IMPROVEMENTS IN THE DUCTILITY OF MOLYBDENUM WELDMENTS BY ALLOYING ADDITIONS OF Zr, B and C
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BASE METAL HEAT AFFECTED ZONE
ATOM PROBE TOMOGRAPHY REVEALSZr, B and C SEGREGATION TO THE GRAIN BOUNDARIES
Research performed byM. K. Miller, Oak Ridge National Laboratoryand A. J. Bryhan, Applied Materials
GIE (atoms m-2)Zr 7.6 x 1013
B 7.3 x 1012
C 1.1 x 1013
O -3.9 x 1012
GIE (atoms m-2)Zr 1.3 x 1013
B 9.9 x 1014
C 9.9 x 1011
O 1.1 x 1013
• Base metal: Zr, C and B enrichments and O depletion• HAZ: Heavy B and moderate Zr enrichments
FIM FIM
APT atom maps
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Three-point bending stress-strain curves forpure tungsten and developed alloys A and B.
Example of the as-rolled sheets.
1
0
2
3
4
1
0
2
3
4
1
0
2
3
4
Stre
ss, σ
(GPa
)
Strain, ε (%) 10%
1
0
2
3
4
1
0
2
3
4
Pure W
Alloy A
Alloy B
473K
513K 583K
200K237K
278K375K
278K 324K 374K
200 300 400 500 600 7000
0.2
0.4
0.6
0.8
1
Abso
rbed
Ene
rgy
(J/m
m3)
?œAlloy A? W-0.2TiC (1999)?€Pure W
?œAlloy A? W-0.2TiC (1999)?€Pure W
Comparison of test temperature dependence of totalabsorbed energy and maximum strength among alloy A,W-0.2wt%TiC and pure tungsten (un-notched bend barimpact tests).
H. Kurishita et al., 2001
Mechanically alloyed W-0.3wt%Ti-0.05wt%Cexhibits good low temperature ductility
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Comparison of Tensile (Red. in area) and CharpyImpact Ductile-Brittle Transition Behavior of Mo-0.5Ti
• The DBTT is dependent on numerous factors, including strain rate and notch acuity(“tensile DBTT” is not a meaningful design parameter)
0
20
40
60
80
100
0
30
60
90
120
150
-100 0 100 200 300 400
Red
uct
ion
in
Are
a (%
)
Imp
act
Str
eng
th (
ft-l
b)
Temperature (˚C)
Stress-relieved
Recrystallized
J.A. Houck, DMIC Report 140 (1960)
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The fusion materials welding program has successfullyresolved one of the key feasibility issues for V alloys
– Results are applicable to other Group V refractory alloys (Nb, Ta)– Use of ultra-high purity weld wire may reduce atmospheric purity requirements
Success is due to simultaneous control of impurity pickup, grain size
-200
-100
0
100
200
300
1992 1994 1996 1998 2000 2002
DB
TT
(˚C
)
Year
V-4Cr-4Ti base metal
GTA welds (no heat treatment)
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Motivation for pursuing Friction Stir Welding (FSW)
• A solid-state joining process such as FSW may enable field weldingof refractory alloys (V, Mo, W), due to reduced pickup ofatmospheric contaminants
• Irradiated materials with He contents above ~1 appm cannot befusion-welded due to cracking associated with He bubble growth;the lower temperatures associated with FSW may allow repairjoining of irradiated materials
0
0.2
0.4
0.6
0.8
1
1.2
1.4
0 0.5 1 1.5 2 2.5 3
Calculated size of He bubbles at grain boundaries in 316 SS
Dia
met
er (
µm)
Time (s)
1400 K
1500 K1600 K
Threshold He bubble size for cracking in 316 SS
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Advanced materials can be successfully joined withfriction stir welding (FSW) process
• Friction stir welding (FSW)uses plastic deformation to joinmaterials.
– Homogeneous microstructureand properties are achieved.
– SiC fibers were uniformlydistributed.
Laser
FSW
Base Metal
Sponsor: DOE Office of Transportation TechnologiesOffice of Heavy Vehicle Technologies
• Metal matrix composites (MMC) and oxide dispersion strengthened (ODS) alloys aredifficult to join using conventional fusion welding processes.
– Particle / fiber reinforcement deteriorate in MMCs due to melting.– In Al-SiC MMC laser welds, SiC decomposes and forms Al4C3 carbides.
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Silicon Carbide Composite Development
Silicon carbide composite is the least-developed of the 3 main structural materialsbeing studied in the Fusion Materials Program, but it has the greatest potential
Very Low Radioactivation - Very High Temperature Use
Areas being actively studied
• Radiation Hardened Composite Development• Effects of Helium on Mechanical Properties
• Radiation Degradation of Thermal Conductivity• Swelling, Amorphization and Defect Fundamentals
Matrix
Fiber
Interphase
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0
0.2
0.4
0.6
0.8
1
1.2
1.4
0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1
No
rmal
ized
Str
ess
(S
irr/
Sa
ve)
Cross Head Displacement (mm)
UnirradiatedStress (MPA), S
aveFiber type
292 (3 tests)Regular Nicalon™359 (7 tests)Hi-Nicalon™416 (2 tests)Type-S Nicalon™
Type-S NicalonComposite
High NicalonComposite
Ceramic Grade Nicalon Composite10 mm
20 mm
2.3 x 6 x 30 mm
FCVI SiC Matrix, C-interphase, Plain Weave Composite~ 1 dpa, HFIR irradiation
ORNL / Kyoto U.
Development of Radiation-Resistant SiC Composites
Ceramic fiber 0.5 µm
SiC-interlayerThin C-interlayer
SiC-interlayer
Bulk SiC
Until recently, SiC/SiC composites exhibited significant degradation inmechanical properties due to non-SiC impurities in fibers causing interfacial debonding.
Upon irradiation, if fibers densify, fiber/matrix interfaces debonds
-->strength degrades300 nm
SiC fiber
SiC multilayersSiC multilayers
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US/Monbusho “Jupiter” Program
We Now Have First Radiation-Resistant SiC Composite
Bend strength of irradiated“advanced” composites showno degradation up to 10 dpa
1st- and 2nd generationirradiated SiC/SiCcomposites show
large strength loss afterdoses >1 dpa
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0
50
100
150
200
250
300
350
400
0 200 400 600 800
Th
erm
al C
ond
uct
ivit
y (W
/m-K
)
Temperature (C)
Type-S Composite (transverse)
P55 Graphite/CVI SiC (high TC)
Morton CVD SiC
K1100 Graphite/CVI SiC (high TC)
High Thermal Conductivity SiC/G Composites offerpotential for improved thermomechanical performance
Fiber K-1100 P-55 Nicalon Type-S
Kth (W/m-K@RT) ~950 120 15Diameter (micron) 10 10 13Tensile Strength (GPa) 3.1 1.9 2.6Tensile Modulus (GPa) 965 379 420Density (g/cc) 2.2 2.0 3.2
Predicted irradiatedconductivity ofSiC/G is higher
than monolithic SiC
Unirradiated
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New Developments in SiC/SiC Fabrication:Nano-Powder Infiltration and Transient Eutectoid (NITE) Process
� Reinforcement� Tyranno™-SA grade-3 (Ube Industries, Ltd.)� Uni-directional� PyC coating, 800nm-thick nominal
� Transient eutectoid process� Uni-axial hot-pressing� Tp ≤ 1800°C� Pp ≤ 20MPa
� Matrix raw materials� Beta-SiC Nano-powder (110m2/g) and
submicron (~40m2/g) powders� Al2O3-Y2O3 complex as sintering additive� Pre-ceramic polymer inclusion
for intra-bundle densification
Institute of Advanced Energy, Kyoto University
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ArP
P
preceramicpyrolysis
Carbon coated TyrannoSA fiber tows
Pre-formingthrough winding
Pre-treatmentby PIP
Matrix coatingby mixed slurry
Drying andstacking
Hot pressing
Characterization
Flow Chart of the “NITE” ProcessInstitute of Advanced Energy, Kyoto University
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“NITE”-Fabricated SiC/SiC
1780C/20MPa
10um
Institute of Advanced Energy, Kyoto University
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Microstructure of “NITE”-Fabricated SiC/SiC
Tyranno™-SA
SiC Matrix
PyC Interphase
Institute of Advanced Energy, Kyoto University
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Fabrication Cost of SiC/SiC by Various Processes
Production cost (k$/kg)
Tota
l Per
form
ance
10
CVI(Mass-Prod.)
10.1
Fiber costAs of Yr.2001Tyranno™-SA
EstimatedMass-production
Fiber costTyranno™-SA
Adv.PIP(Mass-prod.)
Adv.RS/MI (Mass-prod.)
NITEMass-prod.
Fiber cost As of Yr.2001Nicalon™-CG
Adv. RS/MI(Lab-grade)
NITE(Kyoto U.)
PIPConventional
RS/MIConventional
CVIConventional
CVI(Lab-grade)
Institute of Advanced Energy, Kyoto University
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1 03 1 04 1 051 0-5
1 0-4
(b)Flat SiC/SiC composites
F-2
F-1
Pdow
n
Pupper
LPS-2
Tubes by LPS (Kyoto University)
1 03 1 04 1 05
1 0-2
1 0-1
1 00(a) Cylindrical SiC/SiC composites
C-3
C-2
C-1
Pdow
n
Pupper
PIP
PIP+MI
Tyrannohex
Conventional SiC/SiC and Bonded-SiC-Fiber Ceramics
NITE
Permeability of He in SiC/SiCInstitute of Advanced Energy, Kyoto University
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CVI-SiC/SiC
Comparison of Thermal Conductivity of SiC/SiC
0
5
10
15
20
25
30
35
40
0 200 400 600 800 1000 1200 1400
Temperature / C
The
rmal
con
duct
ivity
/ W
/m-K
TySA/PyC/NITE-SiC (1780/20)
TySA/PyC/NITE-SiC (1800/15)
Monolithic-SiC (1780/15*)
Institute of Advanced Energy, Kyoto University
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Mechanical behavior of a wide range of copper alloys hasbeen investigated vs. strain rate and temperature(constitutive equations for deformation and fracture)
0
50
100
150
200
250
0 100 200 300Fra
ctu
re T
ou
gh
nes
s, K
JQ (
MP
a-m
1/2)
Test Temperature (˚C)
CuCrZr
Cu-Al2O3
CuNiBe
CuCrNb
L-T orientation
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100
200
300
400
500
600
700
800
0 200 400 600 800
Ult
imat
e T
ensi
le S
tren
gth
(M
Pa)
Temperature (˚C)
CuCrZr, ITER SAA
CuNiBe, HT1 temper
CuNiBe, AT
GlidCop Al25 (IG0)
1-2x10- 3 s- 1
CuCrNb
• CuNiBe has superior properties below 100˚C; CuCrZr and Cu-Al2O3 have best properties at intermediate temperatures• high temperature limits in CuNiBe and Cu-Al2O3 alloys areassociated with grain boundary phenomena
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0
100
200
300
400
500
600
700
800
0 200 400 600 800
Ult
imat
e T
ensi
le S
tren
gth
(M
Pa)
Temperature (˚C)
CuCrZr, ITER SAA
CuNiBe, HT1 temper
CuNiBe, AT
GlidCop Al25 (IG0)
1-2x10- 3 s- 1
CuCrNb
1 0- 6
1 0- 5
0.0001
0.001
0.01
0.1
0 0.2 0.4 0.6 0.8 1
Deformation Map for CuNiBe (Brush-Wellman Hycon 3HP)
No
rmal
ized
Sh
ear
Str
ess,
τ/µ
(20
˚C)
Normalized Temperature, T/TM
Elastic regime( dε/dt<10-8 s-1)
Coble creep
Dislocation creep
Dislocation glide
Theoretical shear stress limit
20 ˚C 300 ˚C 500 ˚C
1 4
1 4 0
Un
iaxi
al T
ensi
le S
tres
s, M
Pa
1 . 4
1 4 0 0
1 0-8 s-1, L=30 µm
N-H creep
1 0- 6
1 0- 5
0.0001
0.001
0.01
0.1
0 0.2 0.4 0.6 0.8 1
Deformation Map for Oxide Dispersion-strengthened Copper (GlidCop Al25)
No
rmal
ized
Sh
ear
Str
ess,
τ/µ
(20
˚C)
Normalized Temperature, T/TM
Elastic regime( dε/dt<10-8 s-1) Coble creep
Dislocation creep
Dislocation glide
Theoretical shear stress limit
20 ˚C 300 ˚C 500 ˚C
1 4
1 4 0
Un
iaxi
al T
ensi
le S
tres
s, M
Pa
1 . 4
1 4 0 0
1 0-8 s-1, L=5 µm
N-H creep
Applications to US industry (e.g.,USCAR) as well as fusion energysciences program
Mechanical behavior of copper alloys can be understood onthe basis of current materials science models of deformation
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Fiber Type Supplier Remarkscore clad.
Diameter(µm)
RF
JPN
KS-4V
KU-1
KU-H2G
F F
M F
FORC
FORC
FORC
Fujikura Ltd.
MitsubishiCable
200 250
200
200
200
200
250
250
250
250
Pure silica core, OH & Cl free
Original, OH:800ppm
Improved, Hydrogen treatedOH:800ppm
Fluorine doped silica core,OH-free
Fluorine doped silica core,OH-free
Optical fibers for ITER round robin irradiation tests
Team
T. Kakuta et al., ICFRM11 (2001)
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400 600 800 1000 1200 1400 1600
KU-H2GKU-1KS-4VMFFF
Induced Loss (dB
Wavelength (nm)
Comparison of increased absorption in ITER round robin fibers at gamma-ray irradiation of 1.9e6 Gy.
Irrad. source : Cobalt-60 gamma-rayExposure dose : 1.9e6 Gy
Fiber type
0
1.0
2.0
3.0
T. Kakuta et al., ICFRM11 (2001)
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-10
0
10
20
30
40
400 600 800 1000 1200 1400 1600
KS:5.7e20KS:1.0e22KU:5.7e20KU:1.0e22KH:5.7e20KH:1.0e22FF:5.7e20FF:1.0e22MF:5.7e20MF:1.0e22
Induced Loss
Wavelength (nm)
1.0e22 n/m2
5.7e20 n/m2
T. Kakuta et al., ICFRM11 (2001)
Observed Absorption of Optical FibersDuring Fission Neutron Irradiation
High loss in MF fiber may be due to neutron radiation-induced microcracking
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Conclusions
• There is a strong prospect for improvements in the capabilities offusion structural materials based on ongoing research– Nanocomposited ferritic steels– Ductile Mo and W alloys– Hermetic, high conductivity, radiation-resistant, lower cost SiC composites
• Improved joining techniques are being applied to fusion materials– Gas tungsten arc welding of V alloys– Friction stir welding
• Materials which can be categorized as “reduced-activation” haveproperties comparable or superior to their commercial (high-activation) counterparts– e.g., Fe-9Cr ferritic/martensitic steels developed for fusion
• Additional screening studies are needed to identify the mostpromising nonstructural materials for fusion (organic insulators,optical materials, etc.)