Direct pressing: a new method of fabricating MX fuel pellets

Journal Article · Sun Sep 01 04:00:00 EDT 1985 · Nucl. Technol.; (United States)

OSTI ID:5921062

Richter, K; Gueugnon, J; Kramer, G; Sari, C; Werner, P

For fabrication of MX-type (M = actinides; X = carbon and/or nitrogen) advanced fuels, for example, uranium-plutonium carbides for the fast breeder, the carbothermic reduction process of oxides, with subsequent crushing and ballmilling of the reaction product, pressing, and sintering has been generally adopted. A new fabrication procedure, the direct pressing (DP) method, based on the carbothermic reduction process, is presented, however, without intermediate comminution. The fuel is directly processed to pellets. MX powder handling and dust generation within the working area are avoided. The principle and advantages of the new fabrication procedure are reported. The feasibility of the DP method has been demonstrated in laboratory scale on (U,Pu)C fuel pellet preparation. Fuel data compared with the conventional method are given.

• Research Organization: Commission of the European Communities Joint Research Centre, Karlsruhe Establishment European Institute for Transuranium Elements, Karlsruhe
• OSTI ID: 5921062
• Journal Information: Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 70:3; ISSN NUTYB
• Country of Publication: United States
• Language: English

Related Subjects

050700* -- Nuclear Fuels-- Fuels Production & Properties
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
36 MATERIALS SCIENCE
360201 -- Ceramics
Cermets
& Refractories-- Preparation & Fabrication
ACTINIDE COMPOUNDS
CARBIDES
CARBON COMPOUNDS
COMPARATIVE EVALUATIONS
ENERGY SOURCES
FABRICATION
FEASIBILITY STUDIES
FUEL PELLETS
FUELS
MATERIALS
MATERIALS WORKING
MIXED CARBIDE FUELS
NUCLEAR FUELS
PELLETS
PLUTONIUM CARBIDES
PLUTONIUM COMPOUNDS
PRESSING
REACTOR MATERIALS
TRANSURANIUM COMPOUNDS
URANIUM CARBIDES
URANIUM COMPOUNDS