Multiscale modeling of SiCf/SiC nuclear fuel cladding based on FE-simulation of braiding process
Research output: Contribution to journal › Research article › Contributed › peer-review
Contributors
Abstract
A generalized multiscale (micro-macro) finite element (FE) model for SiC-fiber reinforced SiC-matrix ceramic (SiCf/SiC) nuclear fuel claddings is established. In the macro level, the solid mesh of braided preform, which can be tailored by machine settings (braid angle, yarn width, and so on), is generated based on the braiding process simulation using the dynamic FE-solver, hiring the contact constraints. The matrix mesh and the yarn mesh are integrated by the embedded region constraint, with which the meshing difficulties can be avoided. In the micro-UD model, the progressive damage of the ceramic matrix is modeled using the phase field method (PFM) and the fracture is captured by Mohr–Coulombs criterion, which are stable and efficient in the description of the brittle crack initiation, coalition, and branching. Based on this multiscale model, the mechanical behavior of the braided SiCf/SiC nuclear fuel cladding tube is studied in detail. The superiorities over the homogenized tube model are demonstrated, too.
Details
Original language | English |
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Article number | 634112 |
Journal | Frontiers in Materials |
Volume | 7 |
Publication status | Published - 8 Feb 2021 |
Peer-reviewed | Yes |
External IDs
Scopus | 85101276245 |
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ORCID | /0000-0003-1370-064X/work/142243428 |
ORCID | /0000-0003-2653-7546/work/142249308 |
Keywords
Keywords
- SiCf/SiC composite, multiscale model, nuclear fuel cladding, Mohr–Coulombs criterion, phase field method, SiCf/SiC composite, nuclear fuel cladding, multiscale model