AUTHOR=Feng Yajie , Wang Jun , Shang Nianwei , Zhao Gang , Zhang Chao , Tang Jianbo , Xin Shiqing , Hornig Andreas , Gude Maik , Huang Qing , Jian Xigao , Xu Jian 

TITLE=Multiscale Modeling of SiCf/SiC Nuclear Fuel Cladding Based on FE-Simulation of Braiding Process

JOURNAL=Frontiers in Materials

VOLUME=7

YEAR=2021

URL=https://www.frontiersin.org/journals/materials/articles/10.3389/fmats.2020.634112

DOI=10.3389/fmats.2020.634112

ISSN=2296-8016

ABSTRACT=<p>A generalized multiscale (micro-macro) finite element (FE) model for SiC-fiber reinforced SiC-matrix ceramic (SiC<sub>f</sub>/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 SiC<sub>f</sub>/SiC nuclear fuel cladding tube is studied in detail. The superiorities over the homogenized tube model are demonstrated, too.</p>