Abstract
ASTM D7542 provides a standardized way to measure the oxidation mass loss rates of graphite in air within a temperature range where chemical kinetics are assumed to dominate. This test was primarily designed to discriminate between graphite candidates for high-temperature gas-cooled reactors based on their oxidation resistance in air and rate sensitivity to temperature variations. However, data measured according to the recommended procedure are useful beyond making comparisons. Quantification of the rate of oxidation and its effects on microstructure and properties is important for nuclear reactor designers, and it is known that many variables play a role in oxidation. In this work, the measured mass loss curves during oxidation in air are compared to a simplified microstructural oxidation model to provide insight into the contributing mechanisms and to shed light on sources of the scatter commonly seen in oxidation results. Suggestions for improving oxidation standards are made with the hopes of broadening the range of applications and maximizing its utility.
| Original language | English |
|---|---|
| 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 | 257-278 |
| Number of pages | 22 |
| 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 |
|---|---|
| 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 |
|---|---|
| City | Virtual, Online |
| Period | 09/23/21 → 09/24/21 |
Bibliographical note
Publisher Copyright:© 2022 ASTM International. All rights reserved.
Funding
This work was supported by the U.S. Department of Energy (DOE), Office of Nuclear Energy, Advanced Reactor Technology Program. The manuscript was authored by UT-Battelle, LLC, under Contract DE-AC05-00OR22725 with the DOE. The U.S. government retains and the publisher, by accepting the article for publication, acknowledges that the U.S. government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for U.S. government purposes. The DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (http://energy.gov/downloads/doe-public-access-plan).
| Funders | Funder number |
|---|---|
| Advanced Reactor Technology Program | DE-AC05-00OR22725 |
| DOE Public Access Plan | |
| U.S. Government | |
| U.S. Department of Energy | |
| Office of Nuclear Energy |
Keywords
- kinetics
- microstructure
- nuclear graphite
- oxidation
- porosity