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Abstract

Fabrication processes for mixed uranium-plutonium carbide and nitride fuels based on carbothermic reduction of oxides, both with subsequent comminution of the reaction, pressing and sintering, as well as direct pressing of the reacted pellets, are described. The influence of fabrication parameters on fuel composition and properties are given. Results of fuel characterisation by chemical, XRD and ceramographic analysis are discussed with respect to quality control and fuel specification. The data of the He-bonded uranium-plutonium carbide and nitride fuel pins irradiated in the KNKII reactor Karlsruhe, the HFR Petten, and the Phenix reactor at Marcoule, are summarised.

Additional information

Authors: RICHTER K, JRC-KARLSRUHE;BLANK H JRC-KARLSRUHE, JRC-KARLSRUHE
Bibliographic Reference: TECHNICAL COMMITTEE MEETING ON ADVANCED FUEL FOR FAST BREEDER REACTORS, WIEN, NOV. 3-5, 1987, AVAILABILITY: CEC-LUXEMBOURG, DG XIII/A2, BP 1907, MENTIONING PAPER ORA 33803 E
Availability: Can be ordered online
Record Number: 1989126069400 / Last updated on: 1989-05-01
Category: PUBLICATION
Available languages: en