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Micro-Tensile Properties of Irradiated AGR-2 TRISO Fuel Pyrolytic Carbon (PyC) and Silicon Carbide (SiC) Coatings

Year: 2025

Type: article

Abstract: Tristructural isotropic (TRISO) coated nuclear fuel particles are emerging as a versatile option for new reactor designs, with the silicon carbide (SiC) layer crucial for retaining fission products. However, the mechanical properties of TRISO coating layers, particularly after irradiation, are not fully understood due to their small size and high radioactivity. Recent in situ micro-tensile testing of various TRISO layers aims to better understand the SiC layer's failure mechanisms, advancing TRISO fuel qualification. These micro-tensile results will be presented.

Source: OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)

Author: Mauseth, Tanner Jason [Idaho National Laboratory]; Teng, Fei [Idaho National Laboratory]; Cai, Lu [Idaho National Laboratory]; Stempien, John D [Idaho National Laboratory]

Institution: Idaho National Laboratory

Language: English

Topic: Nuclear Materials and Properties

Subfield: Materials Chemistry

Field: Materials Science

Domain: Physical Sciences

Open Access status: green

Funders: U.S. Department of Energy, Battelle, Idaho Operations Office, U.S. Department of Energy

OpenAlex ID: W4406352868

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