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

Kittel, J. H.

doi:10.2172/4068897

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

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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 … continued below

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Kittel, J. H. July 1, 1960.

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This report is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by the UNT Libraries Government Documents Department to the UNT Digital Library, a digital repository hosted by the UNT Libraries. It has been viewed 68 times. More information about this report can be viewed below.

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Kittel, J. H.

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Argonne National Laboratory
Place of Publication: Illinois

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Description

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)

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Other Information: Orig. Receipt Date: 31-DEC-61

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Report No.: ANL-5639
Grant Number: W-31-109-ENG-38
Digital Object Identifier: https://doi.org/10.2172/4068897
Office of Scientific & Technical Information Report Number: 4068897
Archival Resource Key: ark:/67531/metadc871127

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July 1, 1960

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Kittel, J. H. 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, report, July 1, 1960; Illinois. (https://digital.library.unt.edu/ark:/67531/metadc871127/: accessed October 10, 2026), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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

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