Examination of the reactions between oxide and jacket in the G 5 experiment at high burnup ratio

Technical Report · Sun Jul 01 04:00:00 EDT 1973

OSTI ID:4936254

Conte, M; de Keroulas, F; Mikailoff, H

From symposium on fuel and elements for fast reactors; Brussels, Belgium (2 Jul 1973). In order to study the performances of oxides at high burnup and particularly the interactions between oxide and jacket, a fuel element with mixed oxide base (U/sub 0.8/,Pu/sub 0.2)O/sub 1.97/ and clad with 3l6 steel was irradiated with thermal neutrons to a burnup of l25,000 Mwd/t. The irradiation was made in a natural-convection device using NaK, giving a temperature difference between the top and bottom of the fuel element of about 200 deg C throughout the irradiation. Satisfactory behavior of the jacket was verified after the irradiation. Principal results presented are micrographic examination of the structure of the mixed oxide, study of the reactions occurring at the oxide-jacket interface, study of the influence of interior jacket temperature on the thickness of the reaction zones, and microprobe analysis of the constituents of the reaction zone on a sample in which the temperature of the interior of the jacket is about 72O deg C. (tr-auth)

• Research Organization: CEA Centre d'Etudes Nucleaires de Fontenay-aux-Roses, 92 (France)
• Sponsoring Organization: Sponsor not identified
• NSA Number: NSA-29-013063
• OSTI ID: 4936254
• Report Number(s): CEA-CONF--2421; CONF-730726--6
• Country of Publication: France
• Language: French

Related Subjects

BURNUP
COMPATIBILITY
FUEL CANS
FUEL ELEMENTS
HIGH TEMPERATURE
IN PILE LOOPS
LIQUID METALS
N50140* --Metals
Ceramics
& Other Materials--Ceramics & Cermets--Radiation Effects
N79300 --Reactors--Reactor Fuels
NEUTRON BEAMS
PHYSICAL RADIATION EFFECTS
PLUTONIUM OXIDES
POTASSIUM ALLOYS
SODIUM ALLOYS
STAINLESS STEEL-316
THERMAL NEUTRONS
URANIUM DIOXIDE