Fabrication and testing of non-oxide nuclear fuels for fast breeders
Following the development of carbides (U,Pu)C as advanced fuels for fast breeders in the seventies, emphasis is today placed on nitrides (U,Pu)N in Europe and on metallic fuels in the USA, the main motivation being the ease of reprocessing the fuels. The aim is to achieve very high burn-ups with little loss of reactivity during the long in-pile residence time of the fuel. Emphasis in this article is placed on the ceramic European fuel, i.e. the nitrides, though carbides and metallic fuels are also considered. To achieve the desired high burn-up in the nitrides, the otherwise unusual need is to produce a stable ceramic with 15 to 20% porosity. Fabrication procedures, relevant physical and chemical properties and irradiation tests are described.
Bibliographic Reference: Paper presented: 7th CIMTEC World Ceramics Congress, Montecatini-Terme (IT), June 24-30, 1990
Availability: Available from (1) as Paper EN 35609 ORA
Record Number: 199011726 / Last updated on: 1994-12-02
Original language: en
Available languages: en