| About this Abstract |
| Meeting |
2023 TMS Annual Meeting & Exhibition
|
| Symposium
|
Late News Poster Session
|
| Presentation Title |
O-25: Semi-empirical Modeling of Irradiation Induced Dimensional Change of Nuclear Graphites |
| Author(s) |
Steven Johns, William E Windes, Anne A Campbell |
| On-Site Speaker (Planned) |
Steven Johns |
| Abstract Scope |
Nuclear graphite has been used as a moderator material in nuclear reactor designs dating back to the first reactor to reach criticality, Chicago Pile 1 in 1942. In addition, it is anticipated to be used in the conceptual Generation four (GenIV) Molten-salt reactors (MSRs), and the High-temperature gas cooled reactors (HTRs). The macroscopic dimensional change observed in irradiated nuclear graphite is a property change of significant importance. In large part, volumetric change provides valuable insight to the in-service lifetime of graphite components used in nuclear reactors. The dimensional change behavior varies amongst each grade of nuclear graphite due to processing techniques and the resulting microstructure. This work assumes a universal activation energy and an Arrhenius model to predict irradiation dimensional change behavior for all nuclear graphites. |
| Proceedings Inclusion? |
Undecided |
| Keywords |
Nuclear Materials, High-Temperature Materials, |