Planned Fuel Elements the High Flux EL 3 Reactor; ELEMENTS COMBUSTIBLES ENVISAGES POUR LA PILE A HAUT FLUX EL. 3

Technical Report · Fri Oct 30 23:00:00 EST 1959

OSTI ID:4263273

Stohr, J A; Caillat, R; Gauthron, M; Montagne, R

The EL-3 reactor, which is designed as a high-flux materials testing reactor, will use uranium enriched 1.35 to 1.6% and will be cooled by unpressurized heavy water. Studies on the design of the fuel elements are reported. The advantages of an Al-clad U--Mo fuel were investigated. The mechanical stability of the uranium-can interface would be obtained by crimping grooves and thermopneumatic canning. Mechanical tests and heat transfer tests were made, and the results are reported. The possibility of diffusion bonding of the Al was also studied. In this fuel element there would be an intermediate layer of nickel. A zirconium sheath diffusion-bonded to the fuel was examined. The advantages of using a sodium layer between the bare fuel and the can are discussed. An investigation was made of Al-clad UO/sub 2/ pellets. The preparation of the oxide, the effect of the atmosphere on sintering, and the technique of sintering are described. (J.S.R.)

• Research Organization: Commissariat a l'Energie Atomique, Paris
• NSA Number: NSA-13-007135
• OSTI ID: 4263273
• Report Number(s): A/CONF.15/P/1167
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

AIR
ALUMINUM
BONDING
CANNING
DIFFUSION
EL-3
ENRICHMENT
FUEL ELEMENTS
HEAT TRANSFER
HEAVY WATER COOLANT
INERT GASES
MATERIALS TESTING
MECHANICAL PROPERTIES
MOLYBDENUM ALLOYS
NICKEL
PELLETS
PLANNING
PLATES
PLATING
REACTORS
SINTERED MATERIALS
SINTERING
SODIUM
STABILITY
SURFACES
THERMAL CONDUCTIVITY
URANIUM
URANIUM ALLOYS
URANIUM DIOXIDE
ZIRCONIUM
ZONES g.............................