Compatibility of U-Pu-Zr fuels with advanced clad alloys: onset-of-melting results

Technical Report · Sat Feb 01 04:00:00 EST 1986

DOI:https://doi.org/10.2172/711876· OSTI ID:711876

Hins, A. G.

U-Pu-Zr fuels are known to be compatible with stainless steel clads to an upper temperature limit that is constrained by constituent diffusion. At this thermal point the mass transfer of the constituents across the fuel/clad interface creates multicomponent phases that effect liquation, also known as onset-of-melting. Determination of the onset-of-melting temperatures for a number of fuel/clad combinations of interest to the Integral Fast Reactor (IFR) program was the goal of the initial phase of the compatibility work. Fuel/clad compatibility test couples were used to conduct the experiments. Comparisons were made between the present experimental results and the published melting-test results on EBR-II fuel/clad couples and on couples of clad alloys with early U-Pu-Zr fuels. Current experimental results indicate that the IFR advanced fuel/clad couples of primary interest exhibit higher onset-of-melting temperatures than those measured for the fuel/clad combination currently in operation in EBR-II. No unexpected or restrictive chemical interactions between the IFR U-Pu-Zr fuels and advanced clad alloys were found within the temperature range of the tests. 12 figs.

• Research Organization: Argonne National Lab., IL (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 711876
• Report Number(s): ANL-IFR--36; ON: TI86025969
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CHEMICAL COMPOSITION
COMPATIBILITY
FUEL CANS
FUEL-CLADDING INTERACTIONS
LMFBR TYPE REACTORS
METALLOGRAPHY
PLUTONIUM ALLOYS
REACTOR MATERIALS
STAINLESS STEEL-304
URANIUM ALLOYS
ZIRCONIUM ALLOYS