Lanthanide/cladding interdiffusion in IFR fuels

Journal Article · Sat Dec 31 04:00:00 EST 1994 · Transactions of the American Nuclear Society

OSTI ID:75939

Keiser, Jr, D D; Tortorici, P C; Dayananda, M A

Fuel/cladding compatibility has been a main area of focus for Argonne National Laboratory in its development of the Integral Fast Reactor (IFR). The U-Pu-Zr alloy that is employed to power this reactor swells during irradiation and consequently contacts the stainless steel cladding. Subsequently, the fuel components and generated fission products interact with the cladding to form various intermetallic phases, some of which can be low melting and, as a result, can adversely affect the structural integrity of the cladding. The purpose of this investigation was to conduct isothermal, solid-state diffusion anneals of cerium (a prevalent fission product) and stainless steel cladding materials, and compare the relative interdiffusion behavior to that observed in actual IFR systems. Developed diffusion structures were also compared to those reported for earlier cerium interdiffusion studies with iron, nickel, and selected Fe-Ni-Cr alloys.

• OSTI ID: 75939
• Report Number(s): CONF-940602--
• Journal Information: Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 70; ISSN 0003-018X; ISSN TANSAO
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
36 MATERIALS SCIENCE
ALLOY SYSTEMS
AUSTENITIC STEELS
CERIUM
CLADDING
COMPARATIVE EVALUATIONS
DIFFUSION
FAST REACTORS
INTERMETALLIC COMPOUNDS
MARTENSITIC STEELS
NUCLEAR FUELS
PHASE STUDIES
PLUTONIUM ALLOYS
POST-IRRADIATION EXAMINATION
SWELLING
TERNARY ALLOY SYSTEMS
URANIUM ALLOYS
ZIRCONIUM ALLOYS