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Nuclear Materials Research GroupDepartment of Mechanical and Materials Engineering
Levente Balogh1, Fei Long1, Zhongwen Yao1, Michael Preuss2, Hamidreza Abdolvand3, Mark Daymond1
1Department of Mechanical and Materials Engineering, Queen’s University, Kingston, ON, Canada
2The University of Manchester, Manchester Materials Science Centre, Grosvenor Street, Manchester, United Kingdom
3Department of Materials, University of Oxford, UK
Quantifying irradiation defects in Zr alloys: a comparison between transmission electron
microscopy and diffraction line profile analysis
Nuclear Materials Research Group • Department of Mechanical and Materials Engineering • Queen’s University, Kingston, Canada
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Gary S. Was, “Fundamentals of Radiation Materials Science”,Springer Berlin Heidelberg New York, 2007.
Materials properties and microstructure are strongly related
GrowthIrradiation creep
M Griffiths, M.H. Loretto, R.E. SmallmanJ. Nucl. Materials, v115, p313, 1983
Nuclear Materials Research Group • Department of Mechanical and Materials Engineering • Queen’s University, Kingston, Canada
Comparing results by TEM & X-ray in Zr For cold-work dislocations, TEM & X-ray
populations seem to agree well (at low dislocation densities)
For irradiation dislocations, do not agree well, even at low densities.
(qualitatively yes, but not quantitatively) Want to have accurate density numbers for Plasticity models Irradiation creep & growth predictions
relaxation at stress concentration
Nuclear Materials Research Group • Department of Mechanical and Materials Engineering • Queen’s University, Kingston, Canada
Seeing dislocations by TEM & X-rayTEM X-rayDirect view & count Indirect via modelIndividual dislocations PopulationsLaborious / slow to get statistics
Quick & easy to get statistics
Can determine b Need to know possible b: estimateamounts of different b present
Can determine l, with work Can not determine lFCC get screw vs edge ratioHCP <a>:<a+c>:<c> ratio
Good at low to medium densities
Good at all densities (dependent on resolution of instrument)
Thin film effects Bulk average
Nuclear Materials Research Group • Department of Mechanical and Materials Engineering • Queen’s University, Kingston, Canada
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nano-SiC-D sintered at 1820 oC at 8 GPa
nano-SiC-D sinteredat 2320 oC at 8 GPa
L. Balogh, S. Nauyoks, T. W. Zerda, C. Pantea, S. Stelmakh, B. Palosz, T. Ungár,Mater. Sci. Eng. A, 487, (2008) 180‐188.
Diffraction peak widths and shapes are correlated with the microstructure
Nuclear Materials Research Group • Department of Mechanical and Materials Engineering • Queen’s University, Kingston, Canada
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2 2 2 2,exp 2size L gA L A L g L
Fundamental equation of diffraction line broadeningWarren & Averbach:
Fourier transformof a
broadened diffraction peakshape
Contribution ofcrystallite size
distributionContribution of the
microstrain distribution found in the specimen
Warren, B. E. and Averbach, B. L. (1950) J. Appl. Phys. 21, 595.Warren, B. E. (1959) Progr. Metal Phys. 8, 147-202.
Nuclear Materials Research Group • Department of Mechanical and Materials Engineering • Queen’s University, Kingston, Canada
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for dislocation structures : 2,gL
2
2, 4g L
Cb f
0.5
LM
Wilkens, M. (1970b). Phys. Status Solidi A, 2, 359-370.Wilkens, M. (1987). Phys. Status Solidi A, 104, K1.Krivoglaz, M. A. (1969). Theory of X-ray and Thermal Neutron Scattering byReal Crystals. New York: Plenum PressUngár T., Borbély A. Appl. Phys. Lett. 69 (1996) 3173-3175.Ungár T., Tichy G. Phys. Status Solidi A 171 (1999) 425-434.
- Dislocation densityM - Dislocation arrangementC - Dislocation contrast factor => Burgers vector types
0.52
0
lndensME Gb
r
Nuclear Materials Research GroupDepartment of Mechanical and Materials Engineering
TT
M – the dislocation arrangement parameter
random correlated, high dipole character
E. Schafler, et al. Acta Mat. 53 (2005) 315-322.
Mrand Mcorr>>
Nuclear Materials Research Group • Department of Mechanical and Materials Engineering • Queen’s University, Kingston, Canada
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T
gb
T g
b
gb 0dislocation is visible dislocation is invisible
strong contrast weak contrast
gb = 0
strong line broadening weak line broadening
C: the dislocation contrast factor carries information about the Burgers vector types present in the crystal
Nuclear Materials Research Group • Department of Mechanical and Materials Engineering • Queen’s University, Kingston, Canada
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Jostsons, A., Kelly, P. M. and Blake, R. G., Journal of Nuclear Materials, 66 (1977) 236-256
gb 0 gb = 0
The effect of the dislocation contrast factors in TEM
Nuclear Materials Research Group • Department of Mechanical and Materials Engineering • Queen’s University, Kingston, Canada
1111
Physically modeled Experimentally determined
Measured pattern
Ungár T., Borbély A. Appl. Phys. Lett. 69 (1996) 3173-3175.
Ungár T., Tichy G. Phys. Status Solidi A 171 (1999) 425-434.
Ungár T., Gubicza J., Ribárik G., Borbély A. Journal of Applied Crystallography 34 (2001) 298.
Ribárik G., Gubicza J., Ungár T., Mat. Sci. Eng. A 387-389 (2004) 343-347.
IMeas < = > IStrain * ISize * IPlanarFault * IInstr + BG
The quantitative microstructure evaluation is performed using:
eCMWP (extended Convolutional Multiple Whole Profile) method
Nuclear Materials Research Group • Department of Mechanical and Materials Engineering • Queen’s University, Kingston, Canada
12The simultaneous modeling of multiple reflections, measured with high resolution and good counting statistics makes it possible to evaluate
quantitatively the microstructural parameters
G. Ribárik, N. Audebrand, H. Palancher, T. Ungár and D. Louër, J. Appl. Cryst. (2005). 38, 912–926
Nuclear Materials Research Group • Department of Mechanical and Materials Engineering • Queen’s University, Kingston, Canada
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‐ The dislocation loops are approximated with polygons, N=274‐ The contrast factors of the individual edges are calculated using
ANIZC (A. Borbély, J. Dragomir‐Cernatescu, G. Ribárik, T. Ungár, J. Appl. Cryst. 36 (2003) 160‐162. )
Let us account for what we know about radiation defects - specific geometry model
Nuclear Materials Research Group • Department of Mechanical and Materials Engineering • Queen’s University, Kingston, Canada
Contrast factors in hexagonal polycrystalsfor any dislocation type have an hk.l dependence:
where x = (2/3)(l/ga)2 , g = 1/dhk.l
In a hcp polycrystal the dislocation contrast factors can be describedfor any hkl reflection by two parameters: q1 and q2
I. C. Dragomir & T. Ungár, J. Appl Cryst (2002) 35, 556.
Chk.l = Chk.0 [ 1 + q1x + q2x2]
Nuclear Materials Research Group • Department of Mechanical and Materials Engineering • Queen’s University, Kingston, Canada
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The effect of ellipticity on the average contrast factors: <a> type dislocation loop in Zr.
0
0.1
0.2
0.3
0 0.4 0.8 1.2 1.6
1/3<1 1 -2 0>, [1 1 -2 0] a/b = 1/6a/b = 1/2a/b = 1a/b = 2a/b = 6
Aver
age
cont
rast
fact
or
x = (2/3)*(L/ga)^2
Chk.l
10.0 41.1 20.3 31.6 10.3 10.4 00.2
Chk.l = Chk.0 [ 1 + q1x + q2x2]
Nuclear Materials Research Group • Department of Mechanical and Materials Engineering • Queen’s University, Kingston, Canada
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0
0.1
0.2
0.3
0 0.4 0.8 1.2 1.6
dislocations from plasticity<a>-loops, ellipticity of 1.5
Ave
rage
con
trast
fact
or
x = (2/3)*(L/ga)^2
Chk.l
10.0 41.1 20.3 31.6 10.3 10.4 00.2
Contrast for ‘typical’ population of cold‐work dislocations compared to a‐loops
Nuclear Materials Research Group • Department of Mechanical and Materials Engineering • Queen’s University, Kingston, Canada
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<a>, n=[11‐20]g=1‐100
<a>, n=[11‐20]g=01‐10
<a>, n=[11‐20]g=10‐10
Contrast of the <a> loop, b=<11‐20> & n=[11‐20] type when viewed using a 10.0 type reflection
[0001]
Average 10‐10 Average 1‐100Average 01‐10
Nuclear Materials Research Group • Department of Mechanical and Materials Engineering • Queen’s University, Kingston, Canada
18Dislocation loop density from TEM measurements
Jostsons, A., Kelly, P. M. and Blake, R. G., Journal of Nuclear Materials, 66 (1977) 236-256.
Dislocation density:
Δ ∆ ∆ ∆ ∆
Uncertainty of the density:
Nuclear Materials Research Group • Department of Mechanical and Materials Engineering • Queen’s University, Kingston, Canada
19Neutron irradiated Zr-2.5Nb alloy
• Removed from pressure tubes in a CANDU reactor.• Cold worked prior to service.• 7 years of service.• 250C, close to the cooling water inlet.• Neutron fluence 1.6x1024/m2.
Samples provided by:Bruce Power and Chalk River Laboratories, CNL, Canada
Zr‐2.5Nb
Nuclear Materials Research Group • Department of Mechanical and Materials Engineering • Queen’s University, Kingston, Canada
20High resolution time‐of‐flight neutron diffraction measurements performed at theNeutron Powder Diffractometer (NPDF), Lujan Neutron Scattering Center, LANL
• NPDF can be used to collect goodquality data for Line Profile Analysis
d/d 0.15%
• World leader in pair distribution function (pdf) studies
Nuclear Materials Research Group • Department of Mechanical and Materials Engineering • Queen’s University, Kingston, Canada
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9 9.6 10.2 10.8 11.4
Irradiated Zr-2.5NbUnirradiated Zr-2.5Nb
K (1/nm)
20.3 21.0 21.1 11.4 21.2 10.5 21.3
Inte
nsity
(a.u
.)
Significant line profile broadening is observed, which is strongly hk.l dependent
Nuclear Materials Research Group • Department of Mechanical and Materials Engineering • Queen’s University, Kingston, Canada
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0
0.02
0.04
0.06
0.08
4 6 8 10 12
Unirradiated Zr-2.5NbIrradiated Zr-2.5Nb
FWHM
(1/nm
)
K (1/nm)
00.2
21.3
10.5
11.421.110.4
00.4
11.2
10.311.010.2
10.1
21.2
Full‐width at half maximum; Coarse representation of dislocation density / size
Nuclear Materials Research Group • Department of Mechanical and Materials Engineering • Queen’s University, Kingston, Canada
Effect of internal stress distributions not due to dislocations?
Estimate with CPFE calculation
Nuclear Materials Research Group • Department of Mechanical and Materials Engineering • Queen’s University, Kingston, Canada
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0
0.02
0.04
0.06
0.08
4 6 8 10 12
Unirradiated Zr-2.5NbNeutron irradiated Zr-2.5Nb
Simulated residual thermal strains
Simulated residual strains after 4% tensile def (RD)
FWHM
(1/nm
)
K (1/nm)
Possible residual intergranular strains influence the accuracy of LPA measurements less than ~ 10%-15%
Nuclear Materials Research Group • Department of Mechanical and Materials Engineering • Queen’s University, Kingston, Canada
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0
0.02
0.04
0.06
0.08
0 1 2 3 4 5 6
Unirradiated Zr-2.5NbIrradiated Zr-2.5Nb
KC1/2 (1/nm)
FWHM
(1/nm
)
≅0.9
2
Traditional expression1; just using FWHM, not doing full peak-fit
1. Ungár, T. (2008). Powder Diffr. 23, 125–132
Nuclear Materials Research Group • Department of Mechanical and Materials Engineering • Queen’s University, Kingston, Canada
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0
0.04
0.08
0.12
9.5 10 10.5 11
Unirradiated Zr-2.5Nb
Measured pattern (every 2nd point shown)Theoretical patternDifference
Inten
sity (
a. u.)
K (1/nm) 0
0.04
0.08
0.12
9.5 10 10.5 11
Irradiated Zr-2.5Nb
Measured pattern (every 2nd point shown)Theoretical patternDifference
Inten
sity (
a. u.
)K (1/nm)Experimental
dataNon‐
irradiatedIrradiated
q1 0.51 ± 0.05 ‐0.42 ± 0.05
q2 ‐0.43 ± 0.05 ‐0.03 ± 0.05
Full pattern fit - neutron irradiated Zr-2.5Nb alloy
Nuclear Materials Research Group • Department of Mechanical and Materials Engineering • Queen’s University, Kingston, Canada
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Sample Total dislocation density(1014 m‐2)
Dislocations created by plasticity (1014 m‐2)
Density of <a>‐type dislocation
loops(1014 m‐2)
Total ratio of<a> type
ratio of<c+a> type
Non‐irradiated Zr‐2.5Nb
5.8 ± 0.2 5.8 ±0.2
70% ±3%
30% ±3%
N/A
Irradiated Zr‐2.5Nb
20.4 ± 1.1 5.1 ±1.3
15.3 ± 2a/b = 1.5 ± 0.5
Dislocation densities obtained by using theoretical contrast factors specific to irradiation defects
Using cold-work populations to describe radiation: 24 ± 1Using just FWHM: 11 ± 1
Nuclear Materials Research Group • Department of Mechanical and Materials Engineering • Queen’s University, Kingston, Canada
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Foil thickness, h 54 nmAverage loop size, <D> 4.35 nmDensity, 1.0E+15 nm-2
Bright field (BF) and weak‐beam dark field (WBDF) images of the same areaImage pair #5
Nuclear Materials Research Group • Department of Mechanical and Materials Engineering • Queen’s University, Kingston, Canada
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0
20
40
60
80
0 2 4 6 8 10
Numb
er of
loop
s
Dislocation Loop Diameter (nm)
Histogram of the loop diameters measured in image pair #5
<D> = 4.35 nm
Nuclear Materials Research Group • Department of Mechanical and Materials Engineering • Queen’s University, Kingston, Canada
30Image pair # Dislocation
loop density
(1014 m-2)
Mean loop diameter <D>
(nm)
TEM foil thickness
(nm)
1 10.6 3.23 562 11.4 3.69 763 10.3 3.74 564 8.75 3.56 565 10.0 4.35 546 9.29 4.11 557 9.17 4.69 538 9.56 4.15 579 9.28 4.01 7810 8.24 3.72 7811 6.84 4.46 78
Average 9.4Standard deviation
1.17
Eleven BF‐WBDF image pairs were used to calculate the average dislocation density
Nuclear Materials Research Group • Department of Mechanical and Materials Engineering • Queen’s University, Kingston, Canada
31Source of uncertainty
Value Resulting uncertainty of
the dislocation loop density
(1014 m-2)Uncertainty of
<D> (nm)± 0.5 ± 1.18
Uncertainty of h (nm)
± 3 ± 0.45
Relative uncertainty of N
± 0.05 ± 0.47
Relative uncertainty of A
± 0.01 ± 0.09
Total uncertainty of the dislocation loop density
(1014 m-2)
± 2.2
Dislocation loop density from TEM:(9.4 ± 2.2)*1014 m-2
Estimated uncertainty of the dislocation loop density based on error propagation
Nuclear Materials Research Group • Department of Mechanical and Materials Engineering • Queen’s University, Kingston, Canada
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Radiation defect densities obtained by:Transmission Electron
Microscopy (TEM)Diffraction line profile analysis
(DLPA)
(9.4 ± 2.2)x1014 m-2 (15.3 ± 2)x1014 m-2
Nuclear Materials Research Group • Department of Mechanical and Materials Engineering • Queen’s University, Kingston, Canada
33The simulated contrast of a loop:only 2/3 of the loops are visible in a TEM image created with {10.1}
0.6
0.1
Nuclear Materials Research Group • Department of Mechanical and Materials Engineering • Queen’s University, Kingston, Canada
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Radiation defect densities obtained by:TEM TEM, corrected for
the loop contrast effect
Diffraction line profile analysis
(DLPA)
(9.4 ± 2.2)x1014 m-2 (14.1 ± 3.3)x1014 m-2 (15.3 ± 2)x1014 m-2
Nuclear Materials Research Group • Department of Mechanical and Materials Engineering • Queen’s University, Kingston, Canada
35Conclusions & summary
• Diffraction Line Profile Analysis (DLPA) is a powerful tool for the quantitative characterization of the microstructure, including irradiation damage.
• DLPA and microscopy methods (TEM, SEM, …) are complementary characterization techniques.
• Introducing specific microstructure models for irradiation defects can help with the interpretation of the diffraction data
• In this case it was possible to get agreement between the X-ray and TEM. Comparison between more samples irradiated under different conditions is required.
Nuclear Materials Research Group • Department of Mechanical and Materials Engineering • Queen’s University, Kingston, Canada
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Acknowledgements
Thank you for your attention!
Kate Page, LANL, USA
Joan Siewenie, LANL, USA
Malcolm Griffiths, CNL, Canada
Colin Judge, CNL, Canada
Wenjing Li, CNL, Canada