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  5. Improved damage tolerance of SiC-based nuclear fuel cladding with novel multi-layered SiC coating design at 1200 °C

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Article
en
2025

Improved damage tolerance of SiC-based nuclear fuel cladding with novel multi-layered SiC coating design at 1200 °C

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en
2025
Vol 256
Vol. 256
DOI: 10.1016/j.matdes.2025.114260

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Robert O. Ritchie
Robert O. Ritchie

University of California, Berkeley

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Guanjie Yuan
David H. Cook
Harold Barnard
+4 more

Abstract

Continuous SiC fibre reinforced SiC matrix composites (SiCf-SiCm) with monolithic SiC outer coatings are considered as a damage-tolerant cladding design for loss of coolant accident (LOCA) conditions in light water reactors. However, monolithic SiC coatings are brittle and prone to catastrophic failure. In this study, a SiCf-SiCm cladding with a novel multi-layer SiC outer coating (11 sub-layers, ∼260 µm in total thickness) was investigated under C-ring compression at room temperature and 1200 °C in argon environment. Real-time synchrotron X-ray computed tomography (XCT) was employed to capture crack initiation and propagation processes. Compared to conventional monolithic SiC outer coatings, the multi-layer coating structure facilitated crack deflection and bifurcation enhancing its damage tolerance at both temperatures. Despite pre-existing surface cracks, claddings exhibited stable mechanical-performance at both temperatures. These initial cracks did not critically affect the failure processes as they were not aligned with the maximum stress direction. Furthermore, the microstructure, distribution of residual stresses, and local properties of individual components in the material were thoroughly characterized, and compared with open literature on conventional claddings with monolithic outer coatings. These results provide new insights into the failure mechanisms of multi-layer SiC coatings and offer guidance for the future design of accident-tolerant nuclear fuel claddings.

How to cite this publication

Guanjie Yuan, David H. Cook, Harold Barnard, Edward J. Lahoda, Peng Xu, Robert O. Ritchie, Dong Liu (2025). Improved damage tolerance of SiC-based nuclear fuel cladding with novel multi-layered SiC coating design at 1200 °C. , 256, DOI: https://doi.org/10.1016/j.matdes.2025.114260.

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Publication Details

Type

Article

Year

2025

Authors

7

Datasets

0

Total Files

0

Language

en

DOI

https://doi.org/10.1016/j.matdes.2025.114260

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