Abstract
The elastic responses of nuclear graphite not only depend on the graphitic content itself but are largely dictated by the microstructural constitution of the material. The types of raw materials combined with the manufacturing processes used to produce the graphite yield the microstructural content that primarily includes graphite filler, graphitized pitch binder, and voids/defects that typically occupy approximately 20% of the volume. Among these microstructural components, porosity and microcracking (considered to be part of voids/ defects) heavily influence the overall properties of the material, including the elastic moduli. It is widely accepted that the primary effect of oxidation is to increase porosity, but the related effect on the moduli cannot be explained satisfactorily by simply noting changes to porosity. Models describing the elastic moduli of porous, polycrystalline graphite materials have been developed to interpret experimental determinations of Young’s modulus and shear modulus in oxidized graphites. Beyond porosity, the moduli are heavily influenced by microcracks, and their effects can be assessed using physical property models based on orientation distribution coefficients and microcrack-modified, single-crystal moduli to represent the combined effects of crystallite orientation and microcracking. This work demonstrates how most modulus measurements in nuclear graphites can be understood using relatively simple models that describe the effects of porosity and microcracking. We also present directions to be pursued to account for microstructure-related effects that occur as a result of neutron irradiation.
Original language | English |
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Title of host publication | Graphite Testing for Nuclear Applications |
Subtitle of host publication | The Validity and Extension of Test Methods for Material Exposed to Operating Reactor Environments |
Editors | Athanasia Tzelepi, Martin Metcalfe |
Publisher | ASTM International |
Pages | 34-53 |
Number of pages | 20 |
ISBN (Electronic) | 9780803177253 |
DOIs | |
State | Published - 2022 |
Event | 2021 Symposium on Graphite Testing for Nuclear Applications: The Validity and Extension of Test Methods for Material Exposed to Operating Reactor Environments - Virtual, Online Duration: Sep 23 2021 → Sep 24 2021 |
Publication series
Name | ASTM Special Technical Publication |
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Volume | STP 1639 |
ISSN (Print) | 0066-0558 |
Conference
Conference | 2021 Symposium on Graphite Testing for Nuclear Applications: The Validity and Extension of Test Methods for Material Exposed to Operating Reactor Environments |
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City | Virtual, Online |
Period | 09/23/21 → 09/24/21 |
Funding
This research was supported by the U.S. Department of Energy (DOE) through Nuclear Energy University Program Contract No. 00118687. Research at the Oak Ridge National Laboratory was performed collaboratively with Johns Hopkins University under the DOE Work for Others Program.
Keywords
- effective medium
- elastic moduli
- irradiation effects
- microcracks
- nanocracks
- porosity