Determination of the thermal conductivity of an experimental nuclear fuel
The behaviour of metallic fuel types containing minor actinides was studied under irradiation in a fast reactor. The fuel fabrication techniques were tested for different compositions with the aim of producing an homogeneous fuel, with appropriate mechanical and thermal characteristics. The characterisation included elemental analysis, examination and mechanical testing of some candidate fuels, after thermal treatment. Following the tests, two fuels were selected, containing minor actinides and rare earths in equal amounts, either 2 % or 5 %. Their irradiation is planned for 1994 in the Phenix fast reactor (France). The determination of additional parameters was also requested. The mechanical testing, the compatibility studies and the measurement of the thermal conductivity and Young's modulus of the selected alloys were therefore completed.
Bibliographic Reference: Paper presented: E-MRS 1993 Fall Meeting, St. Petersburg (SU), October 17-21, 1993
Availability: Available from (1) as Paper EN 37988 ORA
Record Number: 199311602 / Last updated on: 1994-11-28
Original language: en
Available languages: en