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INGSM-14 Seattle, USA, 15-18 September 2013 Nippon Techno Carbon Co, Ltd Nippon Steel & Sumikin Chemical Pre-irradiation And Specimen Size Effect Study of Nuclear Grade Graphite IGS743NH INGSM-14 September 15-18, 2012 M. Snead (Fechter) 1 , Y. Katoh 1 , N. Cetiner 1 , T. Muto 2 , R. Yamashita 2 , Y. Mitarai 3 1 Oak Ridge National Laboratory 2 Nippon Techno-Carbon 3 Nippon Steel & Sumikin Chemical

Pre-irradiation And Specimen Size Effect Study of Nuclear Grade Graphite IGS743NH

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Pre-irradiation And Specimen Size Effect Study of Nuclear Grade Graphite IGS743NH. INGSM-14 September 15-18, 2012 M. Snead (Fechter) 1 , Y. Katoh 1 , N. Cetiner 1 , T. Muto 2 , R. Yamashita 2 , Y. Mitarai 3 1 Oak Ridge National Laboratory 2 Nippon Techno-Carbon - PowerPoint PPT Presentation

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Page 1: Pre-irradiation And Specimen Size Effect Study of Nuclear Grade Graphite IGS743NH

INGSM-14 Seattle, USA, 15-18 September 2013

Nippon Techno Carbon Co, LtdNippon Steel & Sumikin Chemical

Pre-irradiation And Specimen Size Effect Study of Nuclear Grade Graphite IGS743NH

INGSM-14 September 15-18, 2012M. Snead (Fechter)1, Y. Katoh1, N. Cetiner1,T. Muto2, R. Yamashita2, Y. Mitarai3

1 Oak Ridge National Laboratory2 Nippon Techno-Carbon 3 Nippon Steel & Sumikin Chemical

Page 2: Pre-irradiation And Specimen Size Effect Study of Nuclear Grade Graphite IGS743NH

Managed by UT-Battellefor the U.S. Department of Energy

INGSM-14 Seattle, USA, 15-18 September 20132

Contents

• Program overview– Material and properties to be investigated– Irradiation matrix: fluence and temperature– Rabbit design– Schedule

• ORNL sample size and pre-irradiation program results• Specific gravity• CTE• Thermal conductivity (diffusivity)• Dynamic Young’s and shear moduli• Electrical resistivity• Strength

Page 3: Pre-irradiation And Specimen Size Effect Study of Nuclear Grade Graphite IGS743NH

Managed by UT-Battellefor the U.S. Department of Energy

INGSM-14 Seattle, USA, 15-18 September 20133

Material and Properties to be Investigated

• NTC Graphite Grade IGS-743NH– Iso-molded– Super-fine grained

• Properties to be examined for irradiation effects– Dimensional change– Coefficient of thermal expansion– Thermal conductivity– Electrical resistivity– Dynamic Young’s and shear moduli– Flexural Strength– Tensile strength

Property Unit IGS-743Catalog

Grain size mm <0.05

Density g/cm3 1.80

Flexural Strength MPa 54

Tensile Strength MPa 35

Thermal Conductivity W/m-K 128

CTE (RT-500°C) ppmK-1 4.8

Resistivity Ω-m 12.5

Standard Billet Size mm 350 x 630 x 1020

Page 4: Pre-irradiation And Specimen Size Effect Study of Nuclear Grade Graphite IGS743NH

Managed by UT-Battellefor the U.S. Department of Energy

INGSM-14 Seattle, USA, 15-18 September 20134

Matrix of Irradiation Conditions

Tem

per

atu

re

Fast Fluence, x1025 n/m2

~600ºC

~300ºC

~1000ºC

10

~1200ºC

Prismatic Core

20 30 40

Pebble-bed Core

Page 5: Pre-irradiation And Specimen Size Effect Study of Nuclear Grade Graphite IGS743NH

Managed by UT-Battellefor the U.S. Department of Energy

INGSM-14 Seattle, USA, 15-18 September 20135

Fluence and Temperature in Estimated Irradiation Strain Trend

1Not included in program

1

Page 6: Pre-irradiation And Specimen Size Effect Study of Nuclear Grade Graphite IGS743NH

Managed by UT-Battellefor the U.S. Department of Energy

INGSM-14 Seattle, USA, 15-18 September 20136

Irradiation in HFIR Target Rabbit Facility

• Use of HFIR “rabbit” vehicles allows irradiation of individual tiny capsules at desired temperatures to desired fast neutron fluences.

• Fast flux ~1x1019 n/m2/s, or ~2.1x1025 n/m2 (~1.5 dpa in graphite) during 24-day operating cycle for HFIR.

• Irradiation temperatures 300 to 1300ºC in recent programs.

Page 7: Pre-irradiation And Specimen Size Effect Study of Nuclear Grade Graphite IGS743NH

Managed by UT-Battellefor the U.S. Department of Energy

INGSM-14 Seattle, USA, 15-18 September 20137

Rabbits Design: CTE Beam (CB) and Modulus Beam (MB) Configurations

57.2 mm

57.2 mm

Page 8: Pre-irradiation And Specimen Size Effect Study of Nuclear Grade Graphite IGS743NH

Managed by UT-Battellefor the U.S. Department of Energy

INGSM-14 Seattle, USA, 15-18 September 20138

Rabbit Design: Tensile Configuration – a Challenge

• Limited interior volume in a rabbit capsule– Maximum specimen diameter ~6 mm– Epoxy-extension essential

• Graphite of interest is of high strength – ~35 MPa tensile unirradiated; irradiated strength may be higher– Will require a reduced diameter gauge section

• Miniature tensile specimen geometry is newly developed– 25 mm total length, 6 mm diameter at glued ends– Gauge dimensions Ø 4 mm x L14 mm (L/Ø = 3.5)– Validation study is required

SpecimenMetallic Connector Epoxy Glue here

Page 9: Pre-irradiation And Specimen Size Effect Study of Nuclear Grade Graphite IGS743NH

Managed by UT-Battellefor the U.S. Department of Energy

INGSM-14 Seattle, USA, 15-18 September 20139

Rabbit Design: Tensile Configuration

~50 mm

Page 10: Pre-irradiation And Specimen Size Effect Study of Nuclear Grade Graphite IGS743NH

Managed by UT-Battellefor the U.S. Department of Energy

INGSM-14 Seattle, USA, 15-18 September 201310

Irradiation Program Prospect

• Planning schedule as of September 2013– First rabbits start irradiation on November 19th, 2013– First rabbits will be shipped for post irradiation examination

(PIE) in May 2014– Second shipment of rabbits will be February 2015– Third and last shipment of rabbits will be July 2016

• This is all dependent on the HFIR operation that could change. Currently it is assumed that HFIR operates 6 cycles a year.

Page 11: Pre-irradiation And Specimen Size Effect Study of Nuclear Grade Graphite IGS743NH

Managed by UT-Battellefor the U.S. Department of Energy

INGSM-14 Seattle, USA, 15-18 September 201311

ORNL Pre-Irradiation Evaluation Program:Test Methods

Property MethodASTM

Standard (Graphite)

ASTM Standard

(Ceramics)

Specimen Type

Specimen Dimensions

(mm)

DensityDimensional

inspection and mass

C559 Rectangular Beam

24x3.5x2.25 Etc.

Elastic constants

Sonic resonance C747 C1259 Rectangular

Plate/Beam24x3.5x2.2548x6.0x1.0

CTE Push rod E228 E228 Bar 24x3.5x2.25

Thermal diffusivity Laser flash E1461 E1461 Disc

Ø6 x 1/2/3Ø8 x 2Ø10 x2

Flexural strength Equibiaxial N/A C1499 Coupon 6 x 6 x 0.5

Tensile strength N/a Tensile rod

Gauge dim. Ø6.5 x 26

Ø4 x 14 etc.

Page 12: Pre-irradiation And Specimen Size Effect Study of Nuclear Grade Graphite IGS743NH

Managed by UT-Battellefor the U.S. Department of Energy

INGSM-14 Seattle, USA, 15-18 September 201312

Definition of Orientations for Iso-molded Graphite

X = (with grain) = against gravity = transverse (Tr)

Y = (with grain) = against gravity = transverse (Tr)

Z = (against grain) = with gravity = axial (Ax)

Page 13: Pre-irradiation And Specimen Size Effect Study of Nuclear Grade Graphite IGS743NH

Managed by UT-Battellefor the U.S. Department of Energy

INGSM-14 Seattle, USA, 15-18 September 201313

ORNL Pre-Irradiation Evaluation Program:Specific Gravity

Specimen Type Dimensions No. of

SpecimensAverage (g/cm3)

Std.Dev. (g/cm3) Remarks

CB 24x3.5x2.25 124 1.791 0.006

MB 48x6.0x1.0 64 1.785 0.005

TD6-1 Ø6x1 8 1.788 0.006

TD6-2 Ø6x2 90 1.799 0.007

TD6-3 Ø6x3 8 1.797 0.005

TD8-2 Ø8x2 8 1.794 0.005

TD10-2 Ø10x2 8 1.801 0.004

3SQ6 18x6x0.5 72 1.794 0.008

Tensile various Only gauge diameter and length measured

All 382 1.793 0.008

Page 14: Pre-irradiation And Specimen Size Effect Study of Nuclear Grade Graphite IGS743NH

Managed by UT-Battellefor the U.S. Department of Energy

INGSM-14 Seattle, USA, 15-18 September 201314

Room Temperature Thermal Conductivity

Ax: axial orientation; Tr: transversal orientation;Numbers in parentheses are one standard deviations.

Spec. Type DimensionsThermal

(mm2

Ax.

Diffusivity/ s)

Tr.

Thermal(W /

Ax.

Conductivitym-K)

Tr.TD6-1 Ø6x1 89.7 (1.2) 117.6 (1.6)

TD6-2 Ø6x2 88.4 (0.6) 95.4 (2.5) 116.3 (0.9) 126.2 (3.3)

TD6-3 Ø6x3 86.5 (0.8) 113.9 (1.4)

TD8-2 Ø8x2 89.4 (0.9) 117.6 (1.3)

TD10-2 Ø10x2 87.0 (0.2) 114.9 (0.3)

All 116.2 (1.9) 126.2 (3.3)

Ø10 x 2 mm

Ø8 x 2 mmØ6 x 2 mm

Page 15: Pre-irradiation And Specimen Size Effect Study of Nuclear Grade Graphite IGS743NH

Managed by UT-Battellefor the U.S. Department of Energy

INGSM-14 Seattle, USA, 15-18 September 201315

Thermal ConductivityError bars equal ±1 standard deviations

• Insignificant effect of specimen diameter or thickness.

• Insignificant difference between two orientations.

Page 16: Pre-irradiation And Specimen Size Effect Study of Nuclear Grade Graphite IGS743NH

Managed by UT-Battellefor the U.S. Department of Energy

INGSM-14 Seattle, USA, 15-18 September 201316

Coefficient of Linear Thermal Expansion

Error bars equals 1 standard deviation

CTE Anisotropy Ratio @ 500ºC = ~1.1

Page 17: Pre-irradiation And Specimen Size Effect Study of Nuclear Grade Graphite IGS743NH

Managed by UT-Battellefor the U.S. Department of Energy

INGSM-14 Seattle, USA, 15-18 September 201317

Dynamic Young’s and Shear Moduli

Spec.Type

Dimensions(X x Y x Z)

mmOrient No. of

Tests

Young’sMod.GPa

( Std.Dev. )

ShearMod.GPa

( Std.Dev. ) Poisson’s

Ratio

CB 2.25x3.5x24 AX 64 9.79 ( 0.08 )

CB 24x3.5x2.25 TR 64 10.70 ( 0.09 )

MB 1 x 6 x 48 AX 24 9.58 ( 0.08 ) 4.03 ( 0.13 ) 0.19

MB 48 x 6 x 1 TR 33 10.59 ( 0.09 ) 4.73 ( 0.32 ) 0.12

Type CB specimenType MB specimen

Isotropy ratio = ~1.1

Page 18: Pre-irradiation And Specimen Size Effect Study of Nuclear Grade Graphite IGS743NH

Managed by UT-Battellefor the U.S. Department of Energy

INGSM-14 Seattle, USA, 15-18 September 201318

Electrical Resistivity

Specimen type

Specimen dimensions

X x Y x Z mmOrientation

No. ofTests Electric

ResistivityStandard deviation

CB 2.25x3.5x24 AX 64 11.39 ( 0.13 )

24x3.5x2.25 TR 64 10.45 ( 0.11 )

MB 1 x 6 x 48 AX 24 11.86 ( 0.04 )

48 x 6 x 1 TR 33 10.77 ( 0.05 )

Isotropy ratio = ~1.1

Page 19: Pre-irradiation And Specimen Size Effect Study of Nuclear Grade Graphite IGS743NH

Managed by UT-Battellefor the U.S. Department of Energy

INGSM-14 Seattle, USA, 15-18 September 201319

Flexural Strength - Equibiaxial strength

Dim. (mm)* Orient. Valid

Tests

Normal Average (MPa)

Normal Std.Dev.

(MPa)

Weibull Scale MLE Unbiased

(MPa)

95% LB (MPa)

95% UB (MPa)

Weibull Shape MLE

Unbiased

95% LB

95% UB

6x6x0.5 Tr 30 61.49 2.44 62.52 (61.81 - 63.24) 33.3 (24.9- 44.4)

Specimen type 3SQ6

Page 20: Pre-irradiation And Specimen Size Effect Study of Nuclear Grade Graphite IGS743NH

Managed by UT-Battellefor the U.S. Department of Energy

INGSM-14 Seattle, USA, 15-18 September 201320

Flexural Strength - Equibiaxial strength

• Views are from tensile surface of the specimens.

• Concentric circles indicate approximate locations of contact with the support and loading rings.

• Failure origination from random locations within the loading ring circle indicates sufficiently uniform stress distribution until the initial cracking.

Page 21: Pre-irradiation And Specimen Size Effect Study of Nuclear Grade Graphite IGS743NH

Managed by UT-Battellefor the U.S. Department of Energy

INGSM-14 Seattle, USA, 15-18 September 201321

Tensile Strength: Specimen Size Effect Validation

ID Gauge Diameter Type Orientation Quantity

Full ASTM 6.5 mm Whole piece Axial 30Full ASTM 6.5 mm Whole piece Trans 30

Intermediate 5 mm Whole piece Axial 30

Irradiation size with gauge 4 mm Whole piece Axial 30

Irradiation specimen 4 mm Epoxy glued Axial 30

Smaller than irradiation specimen 3 mm Whole piece Axial 30

Page 22: Pre-irradiation And Specimen Size Effect Study of Nuclear Grade Graphite IGS743NH

Managed by UT-Battellefor the U.S. Department of Energy

INGSM-14 Seattle, USA, 15-18 September 201322

TS4 with Steel Extenders and Alignment Block Setup

Alignment block top

Steel extensor

Alignment block base

V notch Push screw

Page 23: Pre-irradiation And Specimen Size Effect Study of Nuclear Grade Graphite IGS743NH

Managed by UT-Battellefor the U.S. Department of Energy

INGSM-14 Seattle, USA, 15-18 September 201323

Tensile Strength – Preliminary Results

TS6.5U Axial SpecimenX-Y Strain Gauge Reading

Poisson’s ratio: 0.13

• No significant effects of gauge diameter and epoxy-extension.

– More discussion in Katoh et al ASTM paper later this week.

Epoxy-extended Specimens

Unibody Specimens

Page 24: Pre-irradiation And Specimen Size Effect Study of Nuclear Grade Graphite IGS743NH

Managed by UT-Battellefor the U.S. Department of Energy

INGSM-14 Seattle, USA, 15-18 September 201324

Data Comparison for : IGS743NHNTC vs. ORNL Pre-Irradiation Evaluation

• Reasonable agreement has been observed between data generated by NTC and ORNL

Property Unit IGS-743Catalog

IGS-743NHORNL (Tr/Ax) Remarks

Density g/cm3 1.80 1.79 CB specimen for ORNL

Flexural Strength MPa 54 - 3 point bend

Flexural Strength MPa - 61Transverse, Equibiaxial,

miniature

Tensile Strength MPa 35 35 Ø5 – 6.5 mm for ORNL

Thermal Conductivity W/m-K 128 116/126

CTE (RT-500°C) ppmK-1 4.8 4.5/5.0

Resistivity Ohm-m 12.5 10.4/11.4

Young’s Modulus GPa 10.7/9.8 Dynamic for ORNL

Page 25: Pre-irradiation And Specimen Size Effect Study of Nuclear Grade Graphite IGS743NH

Managed by UT-Battellefor the U.S. Department of Energy

INGSM-14 Seattle, USA, 15-18 September 201325

Summary

• ORNL program for evaluation of NTC’s nuclear graphite was initiated and in progress.

• Planned irradiation program will examine baseline physical, thermal, and mechanical properties after fast neutron irradiation up to ~3.2 x 1026 n/m2 at 400 – 1200 ºC. Irradiation vehicles have successfully been developed.

• Pre-irradiation evaluation program is in progress. – All baseline properties are being positively addressed, including

density homogeneity, thermal properties, and strength. – ORNL data are consistent with manufacturer-claimed properties.– Result from tensile specimen size effect study likely validate the

use of small gauge diameter specimens.