Testing of Zircaloy-2-Clad Uranium Seven-Rod Fuel Elements. Final Report

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Description

In 1955 the Fuels Development Operation began irradiation testing of fuel elements in high temperature water. It was assumed that if a new reactor were built at Hanford, it would be cooled by high-temperature, pressurized water. Corrosion tests showed that aluminum-clad production fuel elements could not be used in high-temperature water. Therefore, while work to improve the resistance of aluminum to high-temperature water proceeded, the Fuel Design Operation began irradiation of stainless steel- and Zircaloy-2-clad fuel elements. During 1956 and 1957, stainless steel-clad elements were tested in the Materials Testing Reactor (MTR), Hanford H Reactor Loop, and the KE Reactor … continued below

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27 p.

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Geering, G. T. July 5, 1960.

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  • Hanford Atomic Products Operation
    Publisher Info: General Electric Co., Richland, WA (United States). Hanford Atomic Products Operation
    Place of Publication: Richland, Washington

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Description

In 1955 the Fuels Development Operation began irradiation testing of fuel elements in high temperature water. It was assumed that if a new reactor were built at Hanford, it would be cooled by high-temperature, pressurized water. Corrosion tests showed that aluminum-clad production fuel elements could not be used in high-temperature water. Therefore, while work to improve the resistance of aluminum to high-temperature water proceeded, the Fuel Design Operation began irradiation of stainless steel- and Zircaloy-2-clad fuel elements. During 1956 and 1957, stainless steel-clad elements were tested in the Materials Testing Reactor (MTR), Hanford H Reactor Loop, and the KE Reactor Recirculating (KER) Loops. During 1957, a coextrusion method for cladding uranium rods with Zircaloy-2 was developed. The first irradiation of Zircaloy-2-clad fuel from an off-site supplier began in late 1958. The objective of the irradiation was to study the dimensional stability of the fuel rods and a seven-rod fuel assembly. Two coextruded, seven-rod elements were irradiated in KER Loop l.

Physical Description

27 p.

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OSTI as DE94011991; Paper copy available at OSTI: phone, 865-576-8401, or email, reports@adonis.osti.gov

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  • Other Information: DN: Declassified

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  • July 5, 1960

Added to The UNT Digital Library

  • Nov. 3, 2018, 11:47 a.m.

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  • Nov. 21, 2018, 2:24 p.m.

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Geering, G. T. Testing of Zircaloy-2-Clad Uranium Seven-Rod Fuel Elements. Final Report, report, July 5, 1960; Richland, Washington. (https://digital.library.unt.edu/ark:/67531/metadc1310651/: accessed June 3, 2023), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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