Mechanical and Thermophysical Properties of 3D-Printed SiC-FY20

Technical Report · Fri May 29 04:00:00 EDT 2020

DOI:https://doi.org/10.2172/1632077· OSTI ID:1632077

Byun, T. S. ^[1]; Garrison, Ben E. ^[1]; Wang, Hsin ^[1]; Trofimov, Artem ^[1]; Lach, Tim G. ^[1]; Parish, Chad M. ^[1]; Richardson, M. Dylan ^[1]; Jolly, Brian C. ^[1]; Trammell, Michael ^[1]; Schumacher, Austin ^[1]; Vasudevamurthy, Gokul ^[1]; Koyanagi, Takaaki ^[1]; Terrani, K. A. ^[1]

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1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

In the Transformational Challenge Reactor (TCR), the fuel blocks consist of an additively-manufactured silicon carbide (SiC) matrix and uranium nitride tristructural isotropic (UN TRISO) fuel particles, which are stacked to form fuel columns. The SiC matrix is manufactured using binderjet 3D printing followed by loading the TRISO fuel particles and the chemical vapor infiltration (CVI) process. Because the fuel matrix is a primary component of the TCR core and its response to mechanical and thermal loads during operation is one of the most influential factors on the integrity of TCR core, testing and evaluation have focused on producing mechanical and thermophysical properties data for the binderjet/CVI SiC. Mechanical and thermophysical properties were measured from various types of specimens printed for two or three orientations, which included equibiaxial flexural failure strength, elastic constants, thermal diffusivity and conductivity, density, and the coefficient of thermal expansion. Flexural failure strength datasets showed similar Weibull distributions regardless of sample variants including different orientations. The mean failure strengths of the 3D-printed SiC variants were in the range of 286–306 MPa, which are 22–27% lower than that of the CVD SiC. Thermophysical test results showed that specific heat and thermal expansion are not sensitive to the build directions of SiC samples, while thermal diffusivity is highly dependent on the build direction and can be correlated to the anisotropic character of the 3D-printed SiC. This report also includes discussions on the uniaxial tensile properties of the as-printed SiC before CVI and on ongoing efforts for irradiation effects studies.

• Research Organization: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: AC05-00OR22725
• OSTI ID: 1632077
• Report Number(s): ORNL/SPR-2020/1545
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE