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Abstract

Advanced nuclear fuels + mixed carbides MC, mixed carbonitrides M(C,N), mixed nitrides MN (M = U-0.8Pu-0.2) + show promise for use in future fast breeder reactors (FBR). One precondition for their acceptability as fuels is the mastering of the complete fuel cycle, especially the reprocessing step. In principle, the Purex solvent extraction process, developed for LWR fuel, is also applicable to the recovery of uranium and plutonium from mixed oxide FBR fuel. Additional preparative steps in the head end of the process are needed for advanced fuels, if the reprocessing is based on the controlled oxidation of the fuel to MO-2 with O-2 or CO-2. Another way of preparing the feed to meet the requirements of the Purex process is the direct dissolution of the carbides or nitrides in nitric acid, as described in this paper.

Additional information

Authors: BOKELUND H, JRC KARLSRUHE ESTAB. (GERMANY);GLATZ J P JRC KARLSRUHE ESTAB. (GERMANY), JRC KARLSRUHE ESTAB. (GERMANY)
Bibliographic Reference: 1ST INTERNATIONAL CONFERENCE ON THE CHEMISJTRY AND TECHNOLOGY OF THE LANTHANIDES AND ACTINIDES, VENEZIA (ITALY), SEPT. 5-10, 1983 - WRITE TO CEC LUXEMBOURG, DG XIII/A2, POB 1907 MENTIONING PAPER E 31203 ORA
Availability: Can be ordered online
Record Number: 1989122028200 / Last updated on: 1987-01-01
Category: PUBLICATION
Available languages: en