Chemical compatibility of nuclear fuels with cladding materials

Journal Article · Thu Nov 01 04:00:00 EST 1973 · KFK Nachr., v. 5, no. 3, pp. 7-13

OSTI ID:4309416

Goetzmann, O; Hofmann, P

Investigations in connection with the fast breeder development were carried out using uranium-plutonium mixed oxide and austenitic stainless steel. Carbide and nitride nuclear fuels were also studied along with vanadium alloy cladding materials. The compatibility of the uranium-plutonium mixed oxide is not good as a result of the fission products and the release of oxygen during the irradiation, and will become even more unstable at higher operational temperatures (> 650 deg C on the inner part of the cladding). There is an alternative solution using carbide or carbonitride fuels. Out-of-pile investigations on oxide fuels with getter addition (niobium or zirconium as oxygen binding materials) resulted in diminishing the attack upon the cladding. The effectiveness of the getter, however, can only be finally assessed after irradiation tests on a fuel rod. (GE)

• Research Organization: Kernforschungszentrum, Karlsruhe, Ger.
• NSA Number: NSA-29-024608
• OSTI ID: 4309416
• Journal Information: KFK Nachr., v. 5, no. 3, pp. 7-13, Journal Name: KFK Nachr., v. 5, no. 3, pp. 7-13; ISSN KFKNA
• Country of Publication: Germany
• Language: German

Related Subjects

*NUCLEAR FUELS-- FUEL-CLADDING INTERACTIONS
AUSTENITE
CHEMICAL REACTIONS
COMPATIBILITY
FISSION PRODUCTS
FUEL CANS
FUEL RODS
GETTERING
N50130* --Metals
Ceramics
& Other Materials--Ceramics & Cermets--Properties
Structure & Phase Studies
N79300 --Reactors--Reactor Fuels
OXYGEN
PLUTONIUM OXIDES
STAINLESS STEEL-316
STOICHIOMETRY
URANIUM CARBIDES
URANIUM DIOXIDE
URANIUM NITRIDES
VANADIUM ALLOYS