Fuel Cycle Program. A Boiling Water Reactor Research and Development Program. Eighth Quarterly Progress Report, April-June 1962

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A frequency analysis was made of the VBWR stability test data. Interpretation of the steady-state noise observed in the stability tests involved consideration of several possible sources of excitation. One of these, a theory of water surface waves, is summarized. Visual and destructive examinations were made of selected fuel rods. Fretting corrosion of the Zircaloy-clad fuel rods against stainless steel spacers was observed. Evidence that UO/sub 2/ thermal conductivity increases with time was obtained. Hot gas isotatic pressed fuel rods failed after 316 Mwd/T irradiation and 5 months storage under water. Shakedown operation of a 7-rod test section for measuring … continued below

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75 pages

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Hodde, J.A. comp. July 10, 1962.

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  • Main Title: Fuel Cycle Program. A Boiling Water Reactor Research and Development Program. Eighth Quarterly Progress Report, April-June 1962
  • Serial Title: Fuel Cycle Program Progress Report

Description

A frequency analysis was made of the VBWR stability test data. Interpretation of the steady-state noise observed in the stability tests involved consideration of several possible sources of excitation. One of these, a theory of water surface waves, is summarized. Visual and destructive examinations were made of selected fuel rods. Fretting corrosion of the Zircaloy-clad fuel rods against stainless steel spacers was observed. Evidence that UO/sub 2/ thermal conductivity increases with time was obtained. Hot gas isotatic pressed fuel rods failed after 316 Mwd/T irradiation and 5 months storage under water. Shakedown operation of a 7-rod test section for measuring burnout heat flux was conducted. A comparison of measured and calculated isotopic composition for uranium and plutonium isotopes after 400 Mwd/T irradiation indicated that the calculations underestimate capture in U/sup 238/ and overestimate capture in Pu/ sup 239/. Flux wire irradiations provided axial and radial flux profiles and the ratio of thermal to fast flux as a function of axial position. (M.C.G.)

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75 pages

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  • Other Information: Orig. Receipt Date: 31-DEC-64

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Office of Scientific & Technical Information Technical Reports

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  • July 10, 1962

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  • Sept. 16, 2016, 12:32 a.m.

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  • March 5, 2021, 12:47 a.m.

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Hodde, J.A. comp. Fuel Cycle Program. A Boiling Water Reactor Research and Development Program. Eighth Quarterly Progress Report, April-June 1962, report, July 10, 1962; United States. (https://digital.library.unt.edu/ark:/67531/metadc868871/: accessed December 9, 2023), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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