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in subjects: "Zirconium Alloys"  
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U-Pu-Zr Metal Alloy: a Potential Fuel for LMFBR's

Description: This report critically reviews the available information pertinent to the potential use of uranium-plutonium-zirconium alloy fuels clad with stainless steel in LMFBR's. The areas considered include breeding potential, burnup potential, thermal performance, fuel fabricability, fuel reprocessing, and safety considerations. Because information on uranium-plutonium-zirconium alloys is limited, wide use is made of experience with EBR-II metallic driver fuel to infer advantages and limitations of ura… more
Date: November 1975
Creator: Walter, C. M.; Golden, G. H. & Olson, N. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Fuel Cycle Program Progress Report: January-September 1977

Description: Report of the Argonne National Laboratory Chemical Engineering Division on fuel-cycle studies including pyro-chemical separation of plutonium and americium oxides from contaminated materials of construction such as steel, advanced solvent extraction techniques in the development of centrifugal contactors for use in Purex processes, and a review and evaluation of the encapsulation of high-level waste in a metal matrix.
Date: 1978?
Creator: Steindler, M. J.; Ader, M.; Bernstein, G.; Flynn, K. F.; Gerding, T. J.; Jardine, L. J. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Applied Physical Chemistry Progress Report, October 1991 - September 1992

Description: This document reports on the work done in applied physical chemistry at the Chemical Technology Division (CMT), Argonne National Laboratory (ANL), in the period October 1991 through September 1992. this work includes research into the process that control the release and transport of fission products under accident-like conditions in a light water reactor, the thermophysical properties of the metal fuel in the Integral Fast Reactor under development at ANL, and the properties of candidate triti… more
Date: December 1993
Creator: Johnson, C. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Argonne National Laboratory Fuel Cycle Programs Progress Report: January-March, 1978

Description: Quarterly report of the Argonne National Laboratory Chemical Engineering Division regarding activities related to properties and handling of radioactive materials, operation of nuclear reactors, and other relevant research. This report includes fuel cycle studies in advanced solvent extraction techniques focused on development of centrifugal contactors for use in Purex processes and dispersion of liquids by explosions.
Date: April 1979
Creator: Steindler, M. J.; Ader, M.; Bernstein, G.; Flynn, K.; Gerding, T.; Jardine, L. J. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Chemical Engineering Division Fuel Cycle Programs Progress Report: April-June 1978

Description: Quarterly report of the Argonne National Laboratory Chemical Engineering Division regarding activities related to properties and handling of radioactive materials, operation of nuclear reactors, and other relevant research. This report includes studies on advanced solvent extraction techniques focused on the development of centrifugal contactors for use in Purex processes, extraction kinetics of ruthenium and zirconium in the presence of uranium, and dispersion of uranium and plutonium by fire… more
Date: December 1979
Creator: Steindler, M. J.; Ader, M.; Bernstein, G.; Flynn, K.; Gerding, T.; Jardine, L. J. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Fuel Cycle Programs, Quarterly Progress Report: October-December 1977

Description: Quarterly report of the Argonne National Laboratory Chemical Engineering Division regarding activities related to properties and handling of radioactive materials, operation of nuclear reactors, and other relevant research. This report discusses fuel cycle studies including advanced solvent extraction techniques focused on the development of centrifugal contactors for use in Purex processes, dispersion of reagents as a result of explosions, and identification of organic solutions suitable for … more
Date: 1978?
Creator: Steindler, M. J.; Ader, M.; Bernstein, G.; Flynn, K.; Gerding, T.; Jardine, L. J. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Corrosion of Plutonium Alloys in NaK

Description: A plutonium-aluminum alloy containing 4 atom per cent aluminum showed no attack after exposure to purified NaK for one month at 400 C in the absence of any oxide. The same specimen and other plutonium alloys, including pure plutonium, showed marked deterioration in shorter exposure in the presence of oxide films from a welded stainless steel container. Pure uranium was resistant even in the presence of such oxides.
Date: July 1953
Creator: Hyman, H. H. & Katz, Joseph J. (Joseph Jacob), 1912-2008
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Preliminary Report on Corrosion of Low-Uranium, Zirconium-Base Alloys

Description: Tests were made to determine the effects of heat treatment and composition on the corrosion resistance of low-uranium, zirconium-base alloys to water at 600F. A total of 57 compositions were tested. The zirconium alloys contained up to 9% natural uranium plus small amounts of tin, antimony, lead, bismuth, yttrium, beryllium, germanium, niobium, nickel, and aluminum in various combinations. Data are presented in both tabular and graphical form. The effect of heat treatment on corrosion resistanc… more
Date: October 1953
Creator: Dwight, A. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A Report on Some Attempts to Cast Centrifugally Fuel Elements of Small Diameter

Description: Report issued by the Argonne national Laboratory discussing centrifugal casting of thin uranium plates. The applicability of the centrifugal casting technique to the production of multiple castings of fuel pins of small diameter and of thin fuel plates was investigated. This report includes tables, illustrations, and photographs.
Date: March 1961
Creator: Yaggee, F. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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