Preliminary development of MTR plates with uranium nitride
The first part of this paper presents the work done at the Institute for Transuranium Elements (ITU) concerning the uranium nitride compound and its comparison with the silicide compound. Mixed nitrides are strong candidate fuels for advanced liquid metal cooled fast reactors. They possess the merits of oxide fuels with regard to good irradiation behaviour as well as a high thermal conductivity, higher density of fissile atoms, easy handling during fuel fabrication and storage, and compatibility with the fast reactor coolant sodium. The second part deals with the results of the manufacturing test of MTR plates at CERCA. The most interesting results of this laboratory scale test are given by scanning electron micrographs which show a good comparison between a uranium nitride and a U(3)Si(2) plate.
Bibliographic Reference: Paper presented: International Meeting on Reduced Enrichment for Research and Test Reactors (REHTR), Virginia (US), September 18-23, 1994
Availability: Available from (1) as Paper EN 38673 ORA
Record Number: 199411418 / Last updated on: 1994-12-06
Original language: en
Available languages: en