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

Journal Article · Fri Aug 01 00:00:00 EDT 2025 · Materials & Design

DOI:https://doi.org/10.1016/j.matdes.2025.114260· OSTI ID:2583283

Yuan, Guanjie; Cook, David H; Barnard, Harold; Lahoda, Edward; Xu, Peng; Ritchie, Robert O; Liu, Dong

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.

• Research Organization: Idaho National Laboratory (INL), Idaho Falls, ID (United States); Lawrence Berkeley National Laboratory (LBNL), Berkeley, CA (United States)
• Sponsoring Organization: US Department of Energy; USDOE Office of Nuclear Energy (NE); USDOE Office of Science (SC), Basic Energy Sciences (BES) (SC-22)
• Grant/Contract Number: AC02-05CH11231; AC07-05ID14517
• OSTI ID: 2583283
• Alternate ID(s): OSTI ID: 3029175
• Report Number(s): INL/JOU-25-87180; ark:/13030/qt8vp812s3; https://escholarship.org/uc/item/8vp812s3
• Journal Information: Materials & Design, Journal Name: Materials & Design Vol. 256
• Country of Publication: United States
• Language: English

Related Subjects

36 - MATERIALS SCIENCE
Accident tolerant fuel cladding
Ceramic-matrix composite
Deformation
X-ray computed micro-tomography