Nuclear fuel cladding with high heat conductivity and method for making same

US9031184B2 · kind B2 · utility

Assignee

• COMMISSARIAT A L'ENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES · FR

Inventors

• Julien Cabrero · Salon-de-Provence, FR
• Rene Pailler · Cestas, FR
• Fabienne Audubert · Cadenet, FR

Key dates

• Filing date: Sep 18, 2009
• Grant date: May 12, 2015
• Expiry date: Jul 20, 2031

Classification

• Technology area (CPC Y): Emerging Cross-Sectional Technologies
• CPC primary: Y02E30/30
• WIPO field: Materials, metallurgy
• WIPO sector: Chemistry

Abstract

The invention relates to a nuclear fuel cladding totally or partially made of a composite material with a ceramic matrix containing silicon carbide (SiC) fibers as a matrix reinforcement and an interphase layer provided between the matrix and the fibers, the matrix including silicon carbide as well as at least one of the following additional carbides: titanium carbide (TiC), zirconium carbide (Zrc), and ternary titanium silicon carbide (Ti3SiC2). When irradiated and at temperatures of between 800° C. and 1200° C., said cladding can mechanically maintain the nuclear fuel within the cladding while enabling optimal thermal-energy transfer towards the coolant. The invention also relates to a method for making the nuclear fuel cladding.