Hermeticity of SiC/SiC composite and monolithic SiC tubes irradiated under radial high-heat flux
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
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1. Early-stage diffusion and oxidation behavior of Cr-Nb coated Zr alloy accident tolerant fuel cladding materials at 1200°C–1500°C;Journal of Nuclear Materials;2024-10
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