SiC/graphite System for High-Heat-Flux Applications L. L. Snead 1, M. Balden 2, Rion Causey 3, H Atsumi 4 1 Oak Ridge National Laboratory, Oak Ridge, Tennessee.

Slides:



Advertisements
Similar presentations
Chap.8 Mechanical Behavior of Composite
Advertisements

Presented by: Nassia Tzelepi Progress on the Graphite Crystal Plasticity Finite Element Model (CPFEM) J F B Payne L Delannay, P Yan (University of Louvaine)
HYDROGEN INTERACTION WITH NICKEL CONTAINING RADIOGENIC HELIUM.
Manufacturing Technology
High Temperature Composites Rutgers University Federal Aviation Administration Advanced Materials Flammability Atlantic City, NJ October 24, 2001.
RaDIATE Progress Meeting, May 2013 Graphite progress update BJ Marsden and G Hall Nuclear Graphite Research Group, School of MACE, The University of Manchester.
Distribution of Microcracks in Rocks Uniform As in igneous rocks where microcrack density is not related to local structures but rather to a pervasive.
Engineering materials lecture #14
TOKAI CARBON CO., LTD. Global Leader of Carbon Materials Radiation Effect Study on Tokai Carbon Nuclear Grade Graphite M. Fechter and Y. Katoh Oak Ridge.
Member of the Helmholtz Association Takeshi Hirai | Institute of Energy Research | Association EURATOM – FZJ Cracking of a tungsten material exposed to.
The Effect of Pressure on the Microstructure and Mechanical Properties of Spark Plasma Sintered Silicon Nitride Anne Ellis, Leah Herlihy, William Pinc,
Modeling of CNT based composites: Numerical Issues
A Study of Carbon-Carbon Composites for use in Airplane Disc Brakes
Japan-US Workshop held at San Diego on April 6-7, 2002 How can we keep structural integrity of the first wall having micro cracks? R. Kurihara JAERI-Naka.
for a neutrinos factory
Y. Ueda, M. Fukumoto, H. Kashiwagi, Y. Ohtsuka (Osaka University)
Design of an Aerospace Component
Note on FCI R&D for DEMO for informal discussion DCLL Design Meeting, April 23-24, 2007, UCLA Y. Katoh (ORNL)
Ceramic Structural Composites The Most Advanced Structural Material Lance L Snead Presented at the International School on Fusion Reactor Technology Erice,
March 16-17, 2000ARIES-AT Blanket Design and Power Conversion, US/Japan Workshop/ARR ARIES-AT Blanket Design and Power Conversion The ARIES Team Presented.
Purdue University School of Civil Engineering West West Lafayette, Indiana Autogenous Shrinkage, Residual Stress, and Cracking In Cementitious Composites:
Lab 6B -Fracture Toughness and Fracture Toughness-limited Design Big bang for the buck!
Issues and Prospects of Silicon Carbide Composites for ITER-TBM
Design of Recuperative Heat Exchanger Presented by -- Jinying Zhu.
Materials Science and Development in Support of Inertial Fusion Energy Lance Snead Steven Zinkle Timothy Burchell Oak Ridge National Laboratory Presented.
Computational Nano & Micro Mechanics Laboratory UCLA Measurement of Tungsten Armor - Ferritic Steel Interfacial Bond Strength Using a Nanosecond Laser.
Mechanical Properties
Lead Technology Task 6.2 Materials for mechanical pump for HLM reactors M. Tarantino – ENEA Work Package Meeting – ENEA Bologna, November 17th, 2010.
FAILURE INVESTIGATION OF UNDERGROUND DISTANT HEATING PIPELINE
ZTF Cryostat Finite Element Analysis Andrew Lambert ZTF Technical Meeting 1.
Developing a Vendor Base for Fusion Commercialization Stan Milora, Director Fusion Energy Division Virtual Laboratory of Technology Martin Peng Fusion.
INTRODUCTION The ultimate goal of a manufacturing engineer is to produce steel/metal components with required geometrical shape and structurally optimized.
ME260 Mechanical Engineering Design II Instructor notes.
Tritium Retention in Graphite and Carbon Composites Sandia National Laboratories Rion Causey Sandia National Laboratories Livermore, CA
Design of Concrete Structure I Dr. Ali Tayeh First Semester 2009 Dr. Ali Tayeh First Semester 2009.
MHD/Heat Transfer considerations for SiC FCI in DEMO and ITER Sergey Smolentsev DCLL Special Meeting at UCLA April 23-24, 2007.
Defects in Solids 0-D or point defects –vacancies, interstitials, etc. –control mass diffusion 1-D or linear defects –dislocations –control deformation.
NEEP 541 – Material Properties Fall 2003 Jake Blanchard.
ORNL is managed by UT-Battelle for the US Department of Energy Effects of Neutron Irradiation in IG-110 Y. Katoh, M. Snead, A.A. Campbell Oak Ridge National.
Materials Discussion / Integrated Testing Plan Final Optics Transmissive - issues related to absorption Reflective - LIDT and effect of dust - neutron-induced.
Dimensional Change of Isotropic Graphite under Heavy Ion-Irradiation Sosuke Kondo Makoto Nonaka Tatsuya Hinoki Kyoto University SEP15-18, 2013 INGSM-14.
O AK R IDGE N ATIONAL L ABORATORY U. S. D EPARTMENT OF E NERGY 1 Update on Helium Retention Behavior in Tungsten D. Forsythe, 1 S. Gidcumb, 1 S. Gilliam,
NEEP 541 – Graphite Damage Fall 2002 Jake Blanchard.
Jiangyu Li, University of Washington Yielding and Failure Criteria Plasticity Fracture Fatigue Jiangyu Li University of Washington Mechanics of Materials.
Material Selection in Mechanical Design
1 Nuclear Assessment of HAPL Chamber with Magnetic Intervension Mohamed Sawan Fusion Technology Institute University of Wisconsin, Madison, WI With contributions.
Materials Integration by Fission Reactor Irradiation and Essential Basic Studies for Overall Evaluation Presented by N.Yoshida and K.Abe At the J-US Meeting,
The High- Temperature HTV Graphite Irradiation Capsule for the High Flux Isotope Reactor at Oak Ridge National Laboratory J.L. McDuffee, T.D. Burchell,
PHF110: Basic Physics and Materials Dr Mark A. E. Jepson Room: S227
Reactor pressure vessels of WWER (materials and technology) Janovec, J
ENGINEERING MATERIALS Haseeb Ullah Khan Jatoi Department of Chemical Engineering UET Lahore.
7. Ceramic Matrix Composites Ceramic matrials strenth, stiffness temperature chemical inertness low density sensitive flaw thermal shock Ceramic matrix.
MECHANICAL PROPERTIES OF CERAMICS AND ITS APPLICATION.
Date of download: 5/29/2016 Copyright © ASME. All rights reserved. From: Quantification of Foreign Object Damage and Electrical Resistivity for Ceramic.
SIC FIBERS MECHANICAL AND MICROSTRUCTURAL BEHAVIOR UNDER ION IRRADIATION TUTORS: J.M. COSTANTINI / A. JANKOWIAK / S. MIRO Juan HUGUET-GARCIA 1rst year.
Materials Science Chapter 8 Deformation and Fracture.
TS Cool Down Studies TSu Unit Coils (24-25) N. Dhanaraj and E. Voirin Tuesday, 10 March 2015 Reference: Docdb No:
6.1.3 In Situ Fabrication Techniques -Controlled unidirectional solidification of a eutectic alloy can result in a two-phase microstructure with one of.
Composite Materials Chapter 7. Ceramic Matrix Composites
A. K. Mallik and D. Basu Central Glass and Ceramic Research Institute, Kolkata Effect of processing technologies on grain size and mechanical properties.
MIT Amorphous Materials 8: Mechanical Properties
Dynamic Property Models
Information on Be properties
Dr. Thomas Pozegic Prof. S. R. P. Silva Dr. I. Hamerton
Metal Matrix Composites
Conclusion(Example from Engineering)
Tutorial.
Ceramic Material Grades
Presentation transcript:

SiC/graphite System for High-Heat-Flux Applications L. L. Snead 1, M. Balden 2, Rion Causey 3, H Atsumi 4 1 Oak Ridge National Laboratory, Oak Ridge, Tennessee. USA 2 Max-Planck-Institut für Plasmaphysik, Euratom Association, D Garching, Germany 3 Sandia National Laboratory, Livermore California. USA 4 Kinki University, Osaka, Japan

Goal Production of low activation composite with mechanical performance similar to SiC/SiC but with intrinsically higher thermal conductivity. SiC/Graphite System Advantages, #1: Literature indicates similar or enhanced mechanical properties (strength/toughness) #2: Significant thermal conductivity enhancement. #3: Reduced tritium retention over best carbon fiber composites Disadvantage : Unknown radiation performance and limited manufacturing experience Introduction

Advantage #1: Literature indicates similar or enhanced mechanical properties Tensile Strength (MPa) SiC/SiC Composite (2-D lay-up) SiC/graphite Composite (2-D lay-up) * Strength (and toughness) as good or superior to SiC/SiC

Advantage #2: Significant thermal conductivity enhancement Defect Resistance Thermal conductivity is a function of interstitial migration energy at irradiation temp. Thermal defect resistance term can be used to calculate thermal conductivity of any pure ceramic (ie if grain boundary scattering can be ignored.)

Maximum irradiated thermal conductivity for SiC is estimated to be ~ 10 W/m-K for T < 500°C, ~37 W/m-K at 700°C. Reference Conductivities ARIES 20 W/m-K DREAM W/m-K TAURO 50 W/m-K

SiC/SiC Composite Thermal Conductivity Thermal conductivity of SiC/SiC composites is limited by low conductivity of fiber, low conductivity of matrix, and presence of interfaces (voids, f/m interface, etc.)

T-3 Retention (appm) Irradiation / T-3 Loading Temperature (C) Non-irradiated, infinite charge time Non-Irradiated 1 hr Charge Time High Quality Irradiated CFC (Causey, Snead) Intermediate Quality Irradiated Graphite (Causey, Snead) Advantage #3: Reduced tritium retention over best carbon fiber composites NRL IFE 2/2001 T-3 attaches to basal plane edges and highly defected structure. More perfect material and/or high temperature allows less retention.

Tritium retention, non-irradiated and irradiated, is highly dependent on graphite perfection. K-1100 type fibers are nearly perfect. SiC has very low retention. By replacing the lower perfection matrix of CFC’s with SiC, SiC/graphite will have lower retention. T irr =600°C Tload=1000°C T irr =200°C Tload=1000°C Advantage #3: Reduced tritium retention over best carbon fiber composites Reduced Basal Plane Edge

Engineered High Thermal Conductivity SiC/G Composite Matrix : CVI SiC, no interphase Fibers : Z-direction either Amoco P55 or Thornel K-1100 fiber X-Y direction Amoco P-55 fiber. Total Volume Fraction 44%. FiberK-1100 P-55 Nicalon Type-S Kth ~ Diameter (micron) Tensile Strength (GPa) Tensile Modulus (GPa) Density (g/cc) P55 fiberK1100 fiber Architecture : Unbalanced weave. High TC

SEM Image of Polished SiC/g Surface Good inter-bundle infiltration (5-8% void) Large intra-bundle porosity (13% void) P55 P55 tow

Bend Testing Results Total of 9 tests on CVI SiC/K1100 fiber Ultimate Bend Strength 283 ± 30 MPa Macroscopic Matrix Microcracking ~130 Mpa Published data on SiC/graphite composite report similar strength to SiC/SiC with some reporting up to 800 MPa for T-300 fiber. Published data suggests slightly higher fracture toughness for SiC/graphite. Flexural Strength (MPa) Tensile Strength (MPa)

Temperature Dependent Thermal Conductivity At fusion-relevant temp., SiC/g: --> conductivity exceeds present SiC/SiC --> conductivity exceeds SiC theoretical max. --> Low TC direction on order of SiC/SiC thermal conductivity (for this composite).

Neutron Irradiation Data on Thermal Conductivity CVI SiC/P55 P55 fiber HFIR Irradiation Thermal flash diffusivity Thermal conductivity at measurement temperature

Comparison with High Quality Graphite Degradation Limited data set agrees with degradation expected from high quality graphite modeling.(thermal defect resistance.)

At fusion-relevant temp., SiC/g: --> irradiated TC exceeds max for SiC Application of graphite thermal conductivity degradation model to SiC/K1100

Summary The SiC/graphite systems offer the possibility of acceptable as-irradiated thermal conductivity. Composites are easily made by a number of routes. Materials shown in this study were first attempts using isothermal and forced flow CVI SiC, both of which yielded material of quality comparable to SiC/SiC But… In addition to the issues regarding the use of SiC/SiC composites. here are significant issues regarding the use of this material, including. -- tritium retention -- radiation stability of fiber and overall mechanical lifetime -- effect of fiber shrinkage on thermal conductivity -- erosion and codepositiom issues (if first wall)

Radiation stability of graphite fibers in composites Graphite fiber composites first gain strength (< few dpa) then rapidly lose strength as c-axis expansion causes widespread microcracking Fiber can be expected to shrink axially and swell radially putting interface under tension. Loss in strength may occur due to following: -- micro-cracking length of fiber is < l c ( critical crack length ). -- bundle swelling causes significant matrix microcracking sample surface bundle shrinkage bundle swelling gap 500°C 800°C P55 fiber CFC (FMI-222)

Future Work Understand radiation effects in composites with dissimilar swelling and mechanical property changes. Confirm thermal conductivity degradation is following thermal defect resistance model. Understand tritium retention in very high quality graphite fibers. Composite processing optimization with combined SiC and graphite fibers. Eg. High Nicalon Type S SiC fiber combined with high thermal conductivity Pitch-based graphite fiber.