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Small-scale Approaches to Evaluate the Mechanical Properties of Quasi-brittle Reactor Core Graphite 1 Dong Liu, 1 Peter Heard, 2 Soheil Nakhodchi, 1,3 Peter EJ Flewitt 1 Interface Analysis Centre, School of Physics, University of Bristol, Bristol, BS8 1TL, UK 2 Department of Engineering, University of Bristol, Bristol, BS8 1TR, UK 3 HH Wills Physics Laboratory, University of Bristol, Bristol, BS8 1TL, UK 19 th -20 th September, 2013 1 Symposium on Graphite Testing for Nuclear Applications: the Significance of Test Specimen Volume and Geometry and the Statistical Significance of Test Specimen Population

Small-scale Approaches to Evaluate the Mechanical Properties of Quasi-brittle Reactor Core Graphite 1 Dong Liu, 1 Peter Heard, 2 Soheil Nakhodchi, 1,3

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Page 1: Small-scale Approaches to Evaluate the Mechanical Properties of Quasi-brittle Reactor Core Graphite 1 Dong Liu, 1 Peter Heard, 2 Soheil Nakhodchi, 1,3

Small-scale Approaches to Evaluate the Mechanical Properties of Quasi-brittle Reactor

Core Graphite

1Dong Liu, 1Peter Heard, 2Soheil Nakhodchi, 1,3Peter EJ Flewitt

1Interface Analysis Centre, School of Physics, University of Bristol, Bristol, BS8 1TL, UK2Department of Engineering, University of Bristol, Bristol, BS8 1TR, UK

3HH Wills Physics Laboratory, University of Bristol, Bristol, BS8 1TL, UK

19th-20th September, 2013

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Symposium on Graphite Testing for Nuclear Applications: the Significance of Test Specimen Volume and Geometry and the Statistical Significance of Test Specimen Population

Page 2: Small-scale Approaches to Evaluate the Mechanical Properties of Quasi-brittle Reactor Core Graphite 1 Dong Liu, 1 Peter Heard, 2 Soheil Nakhodchi, 1,3

Content

• Background

• Measurement methods• Four-point bending (centimetre)• Brazilian disc (millimetre)• Micro-scale cantilever (micrometre)• Nano-indentation (micrometre)

• Concluding comments

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19th-20th September, 2013

Symposium on Graphite Testing for Nuclear Applications

Page 3: Small-scale Approaches to Evaluate the Mechanical Properties of Quasi-brittle Reactor Core Graphite 1 Dong Liu, 1 Peter Heard, 2 Soheil Nakhodchi, 1,3

Background

• Important to be able to measure the mechanical properties of both virgin and irradiated graphites.

• Test samples obtained by trepanning from bricks or from monitoring schemes. These provide centimetre scale test specimens.

• Ideally like to reduce specimen size. The use of small scale test specimens offers benefits when handling irradiated reactor core graphite.

• How small can specimens be to achieve representative data.

• Scaling over length is always a challenge.

• Aim to explore the potential benefits, difficulties and value of small scale mechanical tests for this particular application.

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19th-20th September, 2013

Symposium on Graphite Testing for Nuclear Applications

Page 4: Small-scale Approaches to Evaluate the Mechanical Properties of Quasi-brittle Reactor Core Graphite 1 Dong Liu, 1 Peter Heard, 2 Soheil Nakhodchi, 1,3

Background

• Quasi-brittle behaviour

4

PGA graphite

Gilsocarbon graphite

19th-20th September, 2013

Symposium on Graphite Testing for Nuclear Applications

Page 5: Small-scale Approaches to Evaluate the Mechanical Properties of Quasi-brittle Reactor Core Graphite 1 Dong Liu, 1 Peter Heard, 2 Soheil Nakhodchi, 1,3

Four-point bending (PGA graphite)

• Virgin and irradiated PGA graphite

• Cross-section: 25 mm x 25 mm• 20% porosity – virgin PGA graphite• 48% porosity – irradiated PGA graphite

5

150 mm

50 mm

19th-20th September, 2013

Symposium on Graphite Testing for Nuclear Applications

Page 6: Small-scale Approaches to Evaluate the Mechanical Properties of Quasi-brittle Reactor Core Graphite 1 Dong Liu, 1 Peter Heard, 2 Soheil Nakhodchi, 1,3

Four-point bending (PGA graphite)

• Load-displacement curve

• Reloading follows the linear route of the previous cycle

• Residual permanent displacement• Peak load and post peak

softening is visible• Linear variable differential

transformer (LVDT) for vertical displacement measurement

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600 N

900 N

1200 N

Peak load = 1370 N

0.07 mm

19th-20th September, 2013

Symposium on Graphite Testing for Nuclear Applications

Page 7: Small-scale Approaches to Evaluate the Mechanical Properties of Quasi-brittle Reactor Core Graphite 1 Dong Liu, 1 Peter Heard, 2 Soheil Nakhodchi, 1,3

Four-point bending (PGA graphite)

• Mechanical properties (Along the extrusion direction for PGA)

7

Virgin PGA graphite Irradiated PGA graphite

Elastic modulus (GPa) 7.5 ± 0.4 (Ref: 5-15 GPa) < 7.5

Flexural strength (MPa) 13.8 ± 0.6 (Ref: 10-20 MPa) 6.5

19th-20th September, 2013

Symposium on Graphite Testing for Nuclear Applications

Page 8: Small-scale Approaches to Evaluate the Mechanical Properties of Quasi-brittle Reactor Core Graphite 1 Dong Liu, 1 Peter Heard, 2 Soheil Nakhodchi, 1,3

Brazilian disc (Gilsocarbon and PGA graphite)

• Experimental setup

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12 mm

Gilsocarbon graphite

• PGA graphite disc • 12 mm dia. x 6 mm

• Gilsocarbon graphite disc• 12 mm dia. x 6.0 mm• 12 mm dia. x 4.3 mm• 12 mm dia. x 4.0 mm• 12 mm dia. x 3.8 mm

19th-20th September, 2013

Symposium on Graphite Testing for Nuclear Applications

Page 9: Small-scale Approaches to Evaluate the Mechanical Properties of Quasi-brittle Reactor Core Graphite 1 Dong Liu, 1 Peter Heard, 2 Soheil Nakhodchi, 1,3

Brazilian disc (Gilsocarbon and PGA graphite)

• Experimental setup

• South Bay Technology Inc. Model 650 low speed diamond wheel saw

• Deben compression / tensile stage (MicroTest 2000 model, Gatan Ltd., Abingdon, Oxon, UK)

• Compression speeds of between 0.033 and 0.4 mm/min

• Load cell with maximum of 2 KN• Curved anvils with distributed load

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Curved anvilCurved anvil

19th-20th September, 2013

Symposium on Graphite Testing for Nuclear Applications

Page 10: Small-scale Approaches to Evaluate the Mechanical Properties of Quasi-brittle Reactor Core Graphite 1 Dong Liu, 1 Peter Heard, 2 Soheil Nakhodchi, 1,3

Brazilian disc (Gilsocarbon and PGA graphite)

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• Load-displacement curve (12 mm dia. x 6 mm disc)

19th-20th September, 2013

Symposium on Graphite Testing for Nuclear Applications

Page 11: Small-scale Approaches to Evaluate the Mechanical Properties of Quasi-brittle Reactor Core Graphite 1 Dong Liu, 1 Peter Heard, 2 Soheil Nakhodchi, 1,3

Brazilian disc (Gilsocarbon and PGA graphite)

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• Load-displacement curve (12 mm dia. x 4 mm disc)

GILSO

19th-20th September, 2013

Symposium on Graphite Testing for Nuclear Applications

Page 12: Small-scale Approaches to Evaluate the Mechanical Properties of Quasi-brittle Reactor Core Graphite 1 Dong Liu, 1 Peter Heard, 2 Soheil Nakhodchi, 1,3

Brazilian disc (Gilsocarbon and PGA graphite)

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• Mechanical properties (VE=vertical to extrusion direction)

Gilsocarbon graphite PGA graphite (VE)

Elastic modulus (GPa) 2.2 ± 0.4 (Ref: 10 GPa) 1.4 ± 0.3 (Ref: 4.8 GPa)

Tensile strength (MPa) 15.6 ± 1.3 (Ref: 20 MPa) 8.5 ± 1 (Ref: 9 MPa)

400 μm

Fractured surfaceof Gilsocarbon graphite

19th-20th September, 2013

Symposium on Graphite Testing for Nuclear Applications

Page 13: Small-scale Approaches to Evaluate the Mechanical Properties of Quasi-brittle Reactor Core Graphite 1 Dong Liu, 1 Peter Heard, 2 Soheil Nakhodchi, 1,3

Micro-scale cantilever beams (Gilsocarbon)

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• A new approach is developed to prepare beams

• Dualbeam workstation

(FEI Helios NanoLab 600i Workstation)

• Force measurement system (FMS)

(Kleindiek Nanotechnik)

• Select specific microstructure features

Step I

Step II

19th-20th September, 2013

Symposium on Graphite Testing for Nuclear Applications

Page 14: Small-scale Approaches to Evaluate the Mechanical Properties of Quasi-brittle Reactor Core Graphite 1 Dong Liu, 1 Peter Heard, 2 Soheil Nakhodchi, 1,3

Micro-scale cantilever beams (Gilsocarbon)

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5 μm

19th-20th September, 2013

Symposium on Graphite Testing for Nuclear Applications

Page 15: Small-scale Approaches to Evaluate the Mechanical Properties of Quasi-brittle Reactor Core Graphite 1 Dong Liu, 1 Peter Heard, 2 Soheil Nakhodchi, 1,3

Merits of new method

• No tapering

• The root is visible

• Fracture surface exposed

• View specimen throughout the test

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5 μm1 μm

19th-20th September, 2013

Symposium on Graphite Testing for Nuclear Applications

Page 16: Small-scale Approaches to Evaluate the Mechanical Properties of Quasi-brittle Reactor Core Graphite 1 Dong Liu, 1 Peter Heard, 2 Soheil Nakhodchi, 1,3

Loading approach

• Multiple loading cycles

• Vary loading directions

• Imaging at a load on hold

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4 μm

19th-20th September, 2013

Symposium on Graphite Testing for Nuclear Applications

Page 17: Small-scale Approaches to Evaluate the Mechanical Properties of Quasi-brittle Reactor Core Graphite 1 Dong Liu, 1 Peter Heard, 2 Soheil Nakhodchi, 1,3

Loading curves

• Linear → softening → Linear

• Direction dependent properties

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0.0 0.5 1.0 1.5 2.0 2.50

10

20

30

40

Load

(m

N)

Displacement (m)

Load 1 Load 2

Seperatedunloading

Softening region

Load 3

Linear region

Overlapped loading

19th-20th September, 2013

Symposium on Graphite Testing for Nuclear Applications

Page 18: Small-scale Approaches to Evaluate the Mechanical Properties of Quasi-brittle Reactor Core Graphite 1 Dong Liu, 1 Peter Heard, 2 Soheil Nakhodchi, 1,3

Mechanical properties

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Elastic modulus Tensile strength Flexural strength

Gilsocarbon graphite > 20 GPa > 9.8 GPa > 10 GPa

19th-20th September, 2013

Symposium on Graphite Testing for Nuclear Applications

Page 19: Small-scale Approaches to Evaluate the Mechanical Properties of Quasi-brittle Reactor Core Graphite 1 Dong Liu, 1 Peter Heard, 2 Soheil Nakhodchi, 1,3

Nano-indentation

Experimental and specimens

• Cylinder Gilsocarbon graphite specimen (22 mm dia. x 30 mm thickness)

• Agilent Nano Indenter G200(Culham Centre for Fusion Energy, Materials Facility, UK)

• A square array of 5 x 5 of distributed indents are performed on the flat surface

• Berkovich diamond tip

• Load control with the maximum load of 10 mN and peak hold time of 10 s

• Select specific microstructure features

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19th-20th September, 2013

Symposium on Graphite Testing for Nuclear Applications

Page 20: Small-scale Approaches to Evaluate the Mechanical Properties of Quasi-brittle Reactor Core Graphite 1 Dong Liu, 1 Peter Heard, 2 Soheil Nakhodchi, 1,3

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Nano-indentation

Elastic modulus

Gilsocarbon graphite 7.1 - 9.3 GPa

19th-20th September, 2013

Symposium on Graphite Testing for Nuclear Applications

Page 21: Small-scale Approaches to Evaluate the Mechanical Properties of Quasi-brittle Reactor Core Graphite 1 Dong Liu, 1 Peter Heard, 2 Soheil Nakhodchi, 1,3

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Summary of data

Materials Elastic modulus (GPa)

Tensile strength Flexural strength

Four-point bending

PGA (virgin) 7.5 ± 0.4 - 13.8 ± 0.6

PGA (irradiated) < 7.5 - -

Brazilian disc

PGA (virgin) 1.4 ± 0.3 8.5 ± 1 -

Gilsocarbon 2.2 ± 0.4 15.6 ± 1.3 -

Micro-scale cantilever beam

Gilsocarbon > 20 GPa > 9.8 GPa > 10 GPa

Nano-indentation

Gilsocarbon 7.1 - 9.3 - -

19th-20th September, 2013

Symposium on Graphite Testing for Nuclear Applications

Page 22: Small-scale Approaches to Evaluate the Mechanical Properties of Quasi-brittle Reactor Core Graphite 1 Dong Liu, 1 Peter Heard, 2 Soheil Nakhodchi, 1,3

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Concluding comments

• Small-scale testing is a powerful approach to explore mechanical properties of quasi-brittle materials

• Properties measured depend upon length scale of tests

• Centimetre scale tests provide representative global measurements

• Millimetre scale tests could provide representative global values if sufficient tests conducted to sample the material – requires statistical analysis of these data as porosity increases this becomes more difficult

• Micro-scale and below provide measurements for specific micro-scale features

• Important to understand what information is required for a particular application

19th-20th September, 2013

Symposium on Graphite Testing for Nuclear Applications

Page 23: Small-scale Approaches to Evaluate the Mechanical Properties of Quasi-brittle Reactor Core Graphite 1 Dong Liu, 1 Peter Heard, 2 Soheil Nakhodchi, 1,3

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Acknowledgement

We acknowledge the financial support from EPSRC funded project – QUBE

(QUasi-Brittle fracture: a 3D Experimentally-validated approach). Grant number:

EP/J019801/1. The Materials Research Laboratory at the Culham Centre for

Fusion Energy was used for the nano-indentation on Gilsocarbon graphite.

19th-20th September, 2013

Symposium on Graphite Testing for Nuclear Applications

Page 24: Small-scale Approaches to Evaluate the Mechanical Properties of Quasi-brittle Reactor Core Graphite 1 Dong Liu, 1 Peter Heard, 2 Soheil Nakhodchi, 1,3

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19th-20th September, 2013

Symposium on Graphite Testing for Nuclear Applications

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