EFFECTS OF IRRADIATION ON THE EBWR FUEL ALLOY URANIUM-5 w/o ZIRCONIUM-1.5 w/ o NIOBIUM. Final Report-Metallurgy Program 6.1.20

Technical Report · Fri Jul 01 04:00:00 EDT 1960

DOI:https://doi.org/10.2172/4068897· OSTI ID:4068897

Kittel, J. H.

Irradiations were made on small specimens of U-5 wt.% Zr-1.5 wt.% Nb alloy with a wide variety of fabrication histories and heat treatments in order to determine the optimum heat treatment for the fuel plates for the Experimental Boiling Water Reactor (EBW). In the time available, a heat treatment could not be found which simultaneously conferred dimensional stability and corrosion resistance to the alloy. The most effective heat treatment for dimensionally stabilizing swaged or round-rolled material was a 24-hr isothermal transformation from the gamma phase at 650 deg C. This heat treatment was subsequently used as a basis for the heat-treatment specifications for the EBWR fuel plates. In later studies on specimens cut from plates it was learned that the alloy could be adequately stabilized against irradiation growth and also made corrosion- resistent by first reducing the plate 12% in thickness by cold rolling followed by a 24-hr isothermal transformation from the gamma phase at 665 deg C, and finally quenching from 800 deg C. Irradiation growth rates of plate specimens were effectively reduced by the presence of metallurgically bonded Zircaloy-2 cladding. Flat-rolled material under irradiation generally increased in length and width and decreased in thickness. (auth)

• Research Organization: Argonne National Lab., Ill.
• DOE Contract Number: W-31109-ENG-38
• NSA Number: NSA-15-013424
• OSTI ID: 4068897
• Report Number(s): ANL-5639
• Country of Publication: United States
• Language: English

Related Subjects

BOILING
COLD WORKING
CORROSION
EXPANSION
FUEL CANS
FUEL ELEMENTS
HEAT TREATMENTS
IRRADIATION
MATERIALS TESTING
METALS, CERAMICS, AND OTHER MATERIALS
NIOBIUM ALLOYS
PHASE DIAGRAMS
PLATES
RADIATION EFFECTS
REACTORS
ROLLING
STABILITY
URANIUM ALLOYS
WATER COOLANT
WATER MODERATOR
ZIRCALOY
ZIRCONIUM ALLOYS