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Abstract

A solid solution of uranium mononitride and plutonium mononitride (U, Pu, N) is a strong candidate fuel material for advanced LMFBRs. The various stages of a nuclear fuel route for nitrides have been examined - fabrication, in-pile performance and reprocessing. Pellets of (U, Pu, N) with characteristics suitable for irradiation can readily be produced in a standard mixed-oxide facility. When using carbothermic reduction, pressing and sintering, conventionally the process requires a reactive powder. To avoid this, a direct pressing process has been developed in which the reaction product from the carbothermic reduction is fed directly into a press, recompacted and sintered in a conventional alumina muffle furnace. An alternative fabrication process using gelation together with carbothermic reduction is also being studied.

Additional information

Authors: PRUNIER C, CEA/CEN, Cadarache (FR);BARDELLE P, CEA/CEN, Cadarache (FR);RICHTER K, JRC Karlsruhe(DE);STRATTON R W, Scherrer Institut, Villigen (CH);LEDERGERBER G, Scherrer Institut, Villigen (CH)
Bibliographic Reference: Paper presented: 1989 Winter Meeting of the American Nuclear Society, San Francisco (US), Nov. 26-30, 1989
Availability: Available from (1) as Paper EN 35184 ORA
Record Number: 199010920 / Last updated on: 1994-12-01
Category: PUBLICATION
Original language: en
Available languages: en
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