Abstract
Silicon carbide fiber-reinforced silicon carbide matrix (SiC/SiC) composites are among the most promising candidates for long term accident-tolerant nuclear fuel cladding. A key challenge related to their deployment is lateral bowing caused by differential radiation-induced swelling under dose or temperature gradients, which could obstruct coolant flow or interfere with control rod/blade movements. Although previous modeling efforts have predicted bowing behavior in light-water reactor (LWR) environments, experimental validation remains limited, especially at prototypic LWR temperatures. This study addresses that gap by irradiating six reduced-length SiC/SiC cladding tubes (~600 mm) in the High Flux Isotope Reactor (HFIR) at ~300°C, which is representative of LWR conditions. The tubes will be housed in a sealed vessel with an inert gas gap to maintain target temperatures and prevent direct coolant contact. Arranged in three pairs, each set will receive a different radiation dose (low, medium, high), with the central pair receiving ~0.1 displacements per atom (dpa)-the expected dose for peak bowing. The experiment will determine the dose-dependent bowing behavior and validate predictive finite element models. In this work, the tubes are freely suspended from pins to allow for unconstrained bowing; however, we present a concept for introducing localized constraints to represent grid spacer effects. Post-irradiation examination will include swelling measurements and profilometry to assess bowing and compare the results with model predictions. This work aims to confirm the conditions under which maximum bowing occurs so as to improve the reliability of SiC/SiC performance models in nuclear applications.
| Original language | English |
|---|---|
| Title of host publication | Proceedings of the TopFuel 2025 |
| Subtitle of host publication | Nuclear Reactor Fuel Performance Conference |
| Publisher | American Nuclear Society |
| Pages | 702-711 |
| Number of pages | 10 |
| ISBN (Electronic) | 9780894482281 |
| DOIs | |
| State | Published - 2025 |
| Event | TopFuel 2025: Nuclear Reactor Fuel Performance Conference - Nashville, United States Duration: Oct 5 2025 → Oct 9 2025 |
Publication series
| Name | Proceedings of the TopFuel 2025: Nuclear Reactor Fuel Performance Conference |
|---|
Conference
| Conference | TopFuel 2025: Nuclear Reactor Fuel Performance Conference |
|---|---|
| Country/Territory | United States |
| City | Nashville |
| Period | 10/5/25 → 10/9/25 |
Funding
This research was sponsored by the Advanced Fuels Campaign Program of the DOE Office of Nuclear Energy. Neutron irradiation in the High Flux Isotope Reactor is made possible by the DOE Office of Science, Basic Energy Sciences Program. The authors would also like to acknowledge Dillon Cranford for establishing the experiment CAD and drawings, Abby Till for performing the thermal safety calculations, Micheal Crowell for providing HFIR safety guidance and development of the experiment authorization basis document, and Elizabeth Martinez for detailed drawing and thermal model reviews.
Keywords
- bowing
- cladding
- composites
- Silicon carbide
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