Continuous SiC fiber, CVI SiC matrix composites for nuclear applications: Properties and irradiation effects

By Y. Katoh, K. Ozawa, C. Shih, T. Nozawa, R. J. Shinavski, A. Hasegawa, L. Snead. 2014

493 citations recorded by the source corpus.

Subfields: Ceramics and Composites, Mechanical Engineering

View Paper: https://www.semanticscholar.org/paper/be30e0f412f2b518cf49953d7afee3faf73b3f2a

Citations in the corpus

• Neutronic evaluation of coating and cladding materials for accident tolerant fuels (2016, unknown): “SiC cladding is a relatively new concept; manufacturing technologies are still under development, a proven solution to hermetically seal the fuel rod end plugs is yet to be found (Yueh and Terrani, 2014), neutron irradiation induces a reduction in thermal conductivity (Katoh et al., 2014), and recen”