The effect of high-dose neutron irradiation on the properties of graphite and silicon carbide

• Published in: Journal of nuclear materials Vol. 208; no. 1; pp. 1 - 7
• Main Authors: Wu, C.H., Bonal, J.P., Kryger, B.
• Format: Journal Article
• Language: English
• Published: Amsterdam Elsevier B.V 1994; Elsevier
• Subjects: Applied sciences; Energy; Energy. Thermal use of fuels; Exact sciences and technology; Fission nuclear power plants; Installations for energy generation and conversion: thermal and electrical energy; Swelling; Heat capacity; Mechanical properties; Nuclear reactor; Young modulus; Thermal properties; Bending strength; Silicon carbide; Thermal shock resistance; Graphite; Thermal expansion coefficient; Thermal conductivity; Neutron irradiation
• ISSN: 0022-3115; 1873-4820
• DOI: 10.1016/0022-3115(94)90191-0

An experimental study on the effect of neutron irradiation on the properties of graphites and silicon carbides has been carried out using the Phénix reactor. The irradiation temperatures range from 420 to 540°C and the neutron doses are between 14 to 30 dpa. This paper presents the experimental results on the neutron-induced swelling, changes in thermal and mechanical properties of two different ultrafine grain isotropic polygranular graphites and two grades of silicon carbides.