Microstructural Analysis of Nuclear-Grade Graphite …...Microstructural Analysis of Nuclear-Grade...

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Microstructural Analysis of Nuclear-Grade Graphite Materials after Neutron Irradiation after Neutron Irradiation K.Takizawa 1 , Y.Katoh 2 , G.E.Jellison 2 , A.A.Cambell 2 , K.Takizawa , Y.Katoh , G.E.Jellison , A.A.Cambell , 1: Tokai Carbon Co. LTD., Japan 2: Oak Ridge National Laboratory, USA TOKAI CARBON CO., LTD. Global Leader of Carbon Materials

Transcript of Microstructural Analysis of Nuclear-Grade Graphite …...Microstructural Analysis of Nuclear-Grade...

Page 1: Microstructural Analysis of Nuclear-Grade Graphite …...Microstructural Analysis of Nuclear-Grade Graphite Materials after Neutron Irradiation K.Takizawa 1, Y.Katoh 2, G.E.Jellison

Microstructural Analysis of Microstructural Analysis of

Nuclear-Grade Graphite Materials

after Neutron Irradiationafter Neutron Irradiation

K.Takizawa1, Y.Katoh2, G.E.Jellison2, A.A.Cambell2,K.Takizawa , Y.Katoh , G.E.Jellison , A.A.Cambell ,1: Tokai Carbon Co. LTD., Japan

2: Oak Ridge National Laboratory, USA2: Oak Ridge National Laboratory, USA

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Page 2: Microstructural Analysis of Nuclear-Grade Graphite …...Microstructural Analysis of Nuclear-Grade Graphite Materials after Neutron Irradiation K.Takizawa 1, Y.Katoh 2, G.E.Jellison

Graphite for VHTR

Fine grained isotropic graphite

Used as the core structural material of a Very High Temperature gas-cooled Reactor which is

� VHTR has inherent safety features

one of the candidate next generation reactors

� VHTR has inherent safety features

� No meltdown� Slow temperature transient� Slow temperature transient� No chemical reaction

� Outlet gas temperature : 750-1000℃

High process heat can be utilized as a heat source for variety of application

� Outlet gas temperature : 750-1000℃

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heat source for variety of application

Page 3: Microstructural Analysis of Nuclear-Grade Graphite …...Microstructural Analysis of Nuclear-Grade Graphite Materials after Neutron Irradiation K.Takizawa 1, Y.Katoh 2, G.E.Jellison

Neutron Irradiation Damage on Graphite

c-axis

Microscopic changes

c-axis

a-axis

Banhart, F. Rep. Prog. Phys. 1999, 62, 1181–1221.

Macroscopic changes

Re

lati

ve V

olu

me

Ch

an

ge

(%

)R

ela

tive

Vo

lum

e C

ha

ng

e (

%)

turn around

Re

lati

ve V

olu

me

Ch

an

ge

(%

)

contraction expansionContract at first stage then expand

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Fast Neutron Fluence ( x 1026 n/m2, E > 0.1 MeV)Contract at first stage then expand- pores accommodate expansion in c-axis

Page 4: Microstructural Analysis of Nuclear-Grade Graphite …...Microstructural Analysis of Nuclear-Grade Graphite Materials after Neutron Irradiation K.Takizawa 1, Y.Katoh 2, G.E.Jellison

Objective

Graphite materials in nuclear services undergo very significant modifications in various thermal and mechanical properties modifications in various thermal and mechanical properties resulting from the irradiation-induced microstructural changes.

It is essential to characterize the microstructures before and after irradiation and correlate the structural changes with the after irradiation and correlate the structural changes with the evolving macroscopic properties

To characterize the microstructural changes of isotropic fine-grained graphite following the neutron irradiation to help develop graphite for improved radiation service life

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graphite for improved radiation service life

Page 5: Microstructural Analysis of Nuclear-Grade Graphite …...Microstructural Analysis of Nuclear-Grade Graphite Materials after Neutron Irradiation K.Takizawa 1, Y.Katoh 2, G.E.Jellison

Material Information

Nuclear grade graphite G347Amanufactured by Tokai Carbon is used

G347A

manufactured by Tokai Carbon is used for microstructural analysis

G347A is fine-grained, high strength,

100µm

G347A is fine-grained, high strength, isotropic graphite

Dynamic Strength Purity

Typical properties of G347A and ASTM requirements

GradeBulk

density

DynamicElastic

Modulus

StrengthThermal

ConductivityCTE

Purity

Tensile Flexural Compressive AshContent

BoronEquivalent

(g/cm3) (Gpa) (MPa) (MPa) (MPa) (W/m・K) (10-6/K) (ppm) (ppm)(g/cm3) (Gpa) (MPa) (MPa) (MPa) (W/m・K) (10-6/K) (ppm) (ppm)

G347A 1.85 10.8 31.4 49.0 98.0 116 4.9 <5 <0.5

ASTMRequirement

>1.7 8-15 >22 >35 >65 >90 3.5-5.5 <300 <2

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Requirement

Satisfy all ASTM requirements

Page 6: Microstructural Analysis of Nuclear-Grade Graphite …...Microstructural Analysis of Nuclear-Grade Graphite Materials after Neutron Irradiation K.Takizawa 1, Y.Katoh 2, G.E.Jellison

Microstructural Analysis ~ Matrix

Microstructural constituents

Cokes (or binder)

Pores (including cracks)

Cokes (or binder)

Constituents Shape Size Anisotropy Crystallinity

Cokes Raman Raman 2-MGEM Raman Cokes Raman microscopy

Raman microscopy

2-MGEM(ellipsometry)

Raman microscopy

Pores

Image AnalysisX-ray CT Image Analysis

-Pores X-ray CTHg porosimetryN2 adsorption

Image AnalysisX-ray CT

whole SEM, TEMXRD, CTE

Electric resistivityXRD

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whole SEM, TEMElectric resistivity

XRD

Page 7: Microstructural Analysis of Nuclear-Grade Graphite …...Microstructural Analysis of Nuclear-Grade Graphite Materials after Neutron Irradiation K.Takizawa 1, Y.Katoh 2, G.E.Jellison

Dimensional changes after irradiation

Graphite billet

L / L

0(%)

axial⊿L

/ L

axial

Neutron Fuluence(x1025 n/m2 [E > 0.1MeV]) transverse

G347A showed quadratic-like changes

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G347A showed quadratic-like changestemperature dependencyanisotropic changes

Page 8: Microstructural Analysis of Nuclear-Grade Graphite …...Microstructural Analysis of Nuclear-Grade Graphite Materials after Neutron Irradiation K.Takizawa 1, Y.Katoh 2, G.E.Jellison

Microstructural Analysis ~ focal point

� Pores (distribution changes)

Place the focus on 2 properties

� Pores (distribution changes)

Considered to be the most important factor directly related to the dimensional changes (i.e. life time)

� Cokes (orientation changes)

dimensional changes (i.e. life time)

Even isotropic graphite shows definite anisotropic changes

Unirr. Irrad. • shown only in dimensional Unirr. Irrad.

CTE (RT-500C) 4% 4%

Young’s modulus 2% 2%

• shown only in dimensional changes

• more pronounced at higher Dimension - Significant

• more pronounced at higher fluence

To evaluate these properties in detail help understand complicated

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To evaluate these properties in detail help understand complicated changes occurred during irradiation

Page 9: Microstructural Analysis of Nuclear-Grade Graphite …...Microstructural Analysis of Nuclear-Grade Graphite Materials after Neutron Irradiation K.Takizawa 1, Y.Katoh 2, G.E.Jellison

Microstructural Analysis ~ Matrix

Microstructural constituents

Pores (including cracks)

Cokes (or binder)Cokes (or binder)

Constituents Shape Size Anisotropy Crystallinity

Cokes Raman Raman 2-MGEM Raman Cokes Raman microscopy

Raman microscopy

2-MGEM(ellipsometry)

Raman microscopy

Pores

Image AnalysisX-ray CT Image Analysis

-Pores X-ray CTHg porosimetryN2 adsorption

Image AnalysisX-ray CT

whole SEM, TEMXRD, CTE

Electric resistivityXRD

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whole SEM, TEMElectric resistivity

XRD

Page 10: Microstructural Analysis of Nuclear-Grade Graphite …...Microstructural Analysis of Nuclear-Grade Graphite Materials after Neutron Irradiation K.Takizawa 1, Y.Katoh 2, G.E.Jellison

Pore distribution measurement

1.3mm

� The changes of pore distribution are evaluated by optical image analysis

1.3mm

1.1

mm

8 bit gray scale composite image is changed into a set of 256 colored histogram

Composite microstructural image(56 images)

1.1

mm

Minimum evaluation area is 1.6µm2

histogram

As existing pores do not reflect visible light, the dark region is recognized as pores

Pix

els

is recognized as pores⇒ Pores are automatically identified and calculated

Gray Scale LevelIn this study pores less than 5µm2 were disregarded to remove any errors by dot noises in the microscope

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Gray Scale Levelremove any errors by dot noises in the microscope

Page 11: Microstructural Analysis of Nuclear-Grade Graphite …...Microstructural Analysis of Nuclear-Grade Graphite Materials after Neutron Irradiation K.Takizawa 1, Y.Katoh 2, G.E.Jellison

Result : pore distribution

G347A

1

filled markers < 50μm2, open markers > 50μm2

Tota

l por

e nu

mbe

r / (

mm

2 ) -1

G347A

Tota

l por

e nu

mbe

r / (

mm

2 ) -1

Tota

l por

e nu

mbe

r / (

mm

Tota

l por

e nu

mbe

r / (

mm

Tota

l por

e nu

mbe

r / (

mm

Error bar = ±1σ

Tota

l por

e nu

mbe

r / (

mm

Error bar = ±1σError bar = ±1σ Error bar = ±1σ

Neutron Fluence (x1025 n/m2 [E>0.1MeV]) Neutron Fluence (x1025 n/m2 [E>0.1MeV])

Change of the total number showed quadratic-like curve, similar to the dimensional changes

─ Changes of the small pores (<50µm2) are the dominant behavior─ Extinction and generation of pores reaches equilibrium around 15x1025 n/m2

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─ Extinction and generation of pores reaches equilibrium around 15x1025 n/m2

Page 12: Microstructural Analysis of Nuclear-Grade Graphite …...Microstructural Analysis of Nuclear-Grade Graphite Materials after Neutron Irradiation K.Takizawa 1, Y.Katoh 2, G.E.Jellison

Conclusion : pore distribution

• Characteristic changes during irradiation mostly depends on the changes of smaller pores on the changes of smaller pores

• The curve had its vertex around 15x1025 n/m2 which was • The curve had its vertex around 15x10 n/m which was close to the value of average turn around of G347A (300~900ºC, 10~20x1025 n/m2)

• Each result DID NOT show the temperature dependence which dimensional changes clearly showedwhich dimensional changes clearly showed

Undetectable submicron sized pores have a Undetectable submicron sized pores have a temperature dependence and a great influence on dimensional changes?

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Page 13: Microstructural Analysis of Nuclear-Grade Graphite …...Microstructural Analysis of Nuclear-Grade Graphite Materials after Neutron Irradiation K.Takizawa 1, Y.Katoh 2, G.E.Jellison

Orientation measurement

Time-dependent intensity can be expressed as

Intensity(t) = Idc + IX0X0 + IY0Y0 + IX1X1 + IY1Y1 + IX0X1X0X1

+ IX0Y1X0Y1 + IY0X1Y0X1 + IY0Y1Y0Y1

Two of eight coefficients of the basis functions are used to evaluate graphite orientation

i.e. IY0 = sin(2γ)N

Sample

i.e. IY0 = sin(2γ)N

IY1 = -con(2γ)N

IY0, IY1 = coefficients of basis function,

2-MGEM

Y0, Y1γ = principal axis, N = diattenuation

Preferential orientation of the principal (2- Modulator Generalized Ellipsometry Microscope)

2-MGEM is configured as a reflection microscope at near-normal incidence and measures eight different parameters*

Preferential orientation of the principal axis in graphite is parallel to the a-axis(perpendicular to the c-axis)

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measures eight different parameters*

*G. E. Jellison, Jr. and J. D. Hunn, “Optical anisotropy measurements of TRISO nuclear fuel particle cross-sections: The method” J. Nuclear Mat. 372, 36-44, (2008)

Page 14: Microstructural Analysis of Nuclear-Grade Graphite …...Microstructural Analysis of Nuclear-Grade Graphite Materials after Neutron Irradiation K.Takizawa 1, Y.Katoh 2, G.E.Jellison

Orientation measurement

Principal axis angle collections are converted into histogram and normalized for calculation

1-a(amplitude)

0.5mm Co

un

ts

18

(amplitude)

γ

Pri

nci

pa

l A

xis

An

gle

Fast Axis Angle(°)

Count(nor.) = (1-a)sinn (2(x-b))+a

Each histogram was fitted with sign curve;

Pri

nci

pa

l A

xis

An

gle

Fast Axis Angle(°)

Graphite orientation was estimated by the value of amplitude for simple evaluation

Count(nor.) = (1-a)sinn (2(x-b))+aPri

nci

pa

l A

xis

An

gle

0.5

mm

reference plane°

FAA

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value of amplitude for simple evaluation0.5

mm

Mapping results of G347A(pixel size:□5μm)

reference plane0°

Page 15: Microstructural Analysis of Nuclear-Grade Graphite …...Microstructural Analysis of Nuclear-Grade Graphite Materials after Neutron Irradiation K.Takizawa 1, Y.Katoh 2, G.E.Jellison

Result : Comparison with XRD method

� Orientation function I (φ) based on the diffraction curves of (002) were calculated by using X-ray diffractometer to compare with the results obtained by 2-MGEM

The diffraction pattern of (002) for two characteristic graphite (G347A, Graphite A) were obtained as a function of rotating angle

y

), n

orm

.

Counter

(fixed)zφ

1.0

0.8

zx

y

I (

φ),

no

rm.

(fixed)

X-ray

Specimen(rotating)

θ002

θ002

zx

θ002

φ0.6

0.4

0.2

axial

Amplitude

Φ1mm x 8 mm

φ (deg.)

Specimen(rotating)0.0

20 40 60 80 100 120 140 160

2-MGEM : y-z plane was measuredGrade

Amplitude

XRD 2-MGEM*

G347A 0.18 0.332-MGEM method showed the same trend as XRD method indicating its availability for orientation

2-MGEM : y-z plane was measured

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Graphite A 0.24 0.54

method indicating its availability for orientation evaluation

Page 16: Microstructural Analysis of Nuclear-Grade Graphite …...Microstructural Analysis of Nuclear-Grade Graphite Materials after Neutron Irradiation K.Takizawa 1, Y.Katoh 2, G.E.Jellison

Result : orientation

� Irradiated graphite (G347A, 750ºC) were evaluated by using 2-MGEMD

imen

sion

al c

hang

e / %

G347A(750℃)_axial

Dim

ensi

onal

cha

nge

/ %

Measurementspecimen

Am

plitu

de /

-

Dim

ensi

onal

cha

nge

/ %

Am

plitu

de /

Neutron Fluence (x1025 n/m2 [E>0.1MeV])Neutron Fluence (x1025 n/m2 [E>0.1MeV]) Neutron Fluence (x1025 n/m2 [E>0.1MeV])Neutron Fluence (x1025 n/m2 [E>0.1MeV])

Increment of amplitude was observed with increasing neutron fluence─ Internal orientation became more anisotropic after irradiation

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─ This tendency well agree with the anisotropic dimensional changes

Page 17: Microstructural Analysis of Nuclear-Grade Graphite …...Microstructural Analysis of Nuclear-Grade Graphite Materials after Neutron Irradiation K.Takizawa 1, Y.Katoh 2, G.E.Jellison

Conclusion : orientation

• 2-MGEM is of use in evaluating graphite • 2-MGEM is of use in evaluating graphite orientation having the advantage in terms of sensitivity to preferential orientation compared with the XRD method

axi

al

• G347A showed more anisotropic properties after

with the XRD method

z

y

axi

al

• G347A showed more anisotropic properties after irradiation agreeing with anisotropic dimensional changes

x

y

• 2-MGEM measurement indicated the possibility that rearrangement of cokes particles occurred by that rearrangement of cokes particles occurred by shrinkage

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Page 18: Microstructural Analysis of Nuclear-Grade Graphite …...Microstructural Analysis of Nuclear-Grade Graphite Materials after Neutron Irradiation K.Takizawa 1, Y.Katoh 2, G.E.Jellison

Summary

Focused on pore distribution/orientation changes during irradiation

� Pore changes observed as a function of neutron fluence had the same tendency as what dimensional changes had shown

We have to come up with another method to investigate the thermal sensitive element with statistical volume

� Shrinkage during irradiation lead to rearrangement of internal crystal strengthening the originally existing preferential orientation

─ Crystallographic orientation is not vital for mechanical/thermal anisotropic properties?

Still unclear why mechanical /thermal measurements showed isotropic properties even after irradiation

In our recent study with unirradiated graphite, BAFs obtained by XRD showed a different trend than that of mechanical/thermal properties

─ Crystallographic orientation is not vital for mechanical/thermal anisotropic properties?

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different trend than that of mechanical/thermal properties

Page 19: Microstructural Analysis of Nuclear-Grade Graphite …...Microstructural Analysis of Nuclear-Grade Graphite Materials after Neutron Irradiation K.Takizawa 1, Y.Katoh 2, G.E.Jellison

Thank you for your attention!Thank you for your attention!

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