MECHANISMS AND KINETICS OF URANIUM CORROSION AND URANIUM CORE FUEL ELEMENT RUPTURES IN WATER AND STEAM

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Description

The mechanisms and kinetics of uranium corrosion and fuel element ruptures were investigated in water and steam at 170 to 500 deg C and at 100 to 2800 psig. The fuel element samples were coextruded Zircaloy-clad uranium-core rods and tubes which were defected prior to exposure. Uranium corrosion was found to be the sum of two processes; direct oxidation by water, and oxidation of uranium hydride intermediate. Fuel element ruptures occur in two stages; an initial induction period followed by an accelerating corrosion of the core causing the cladding to blister, swell, and fracture. Uranium corrosion and fuel element ruptures ... continued below

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Pages: 94

Creation Information

Troutner, V.H. July 21, 1960.

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  • Hanford Atomic Products Operation
    Publisher Info: General Electric Co. Hanford Atomic Products Operation, Richland, Wash.
    Place of Publication: Richland, Washington

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Description

The mechanisms and kinetics of uranium corrosion and fuel element ruptures were investigated in water and steam at 170 to 500 deg C and at 100 to 2800 psig. The fuel element samples were coextruded Zircaloy-clad uranium-core rods and tubes which were defected prior to exposure. Uranium corrosion was found to be the sum of two processes; direct oxidation by water, and oxidation of uranium hydride intermediate. Fuel element ruptures occur in two stages; an initial induction period followed by an accelerating corrosion of the core causing the cladding to blister, swell, and fracture. Uranium corrosion and fuel element ruptures were examined with respect to temperature, pressure, steam versus liquid water, heat treatment, carbon content of uranium, zirconium content of uranium, cladding thickness, fuel geometry, annular spacings, defect geometry and size, coolant flow, hydriding of Zircaloy components, and irradiation effects. (auth)

Physical Description

Pages: 94

Source

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

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  • Report No.: HW-67370
  • Grant Number: AT(45-1)-1350
  • DOI: 10.2172/4023654 | External Link
  • Office of Scientific & Technical Information Report Number: 4023654
  • Archival Resource Key: ark:/67531/metadc872551

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Office of Scientific & Technical Information Technical Reports

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Creation Date

  • July 21, 1960

Added to The UNT Digital Library

  • Sept. 16, 2016, 12:32 a.m.

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  • Feb. 20, 2017, 4:15 p.m.

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Troutner, V.H. MECHANISMS AND KINETICS OF URANIUM CORROSION AND URANIUM CORE FUEL ELEMENT RUPTURES IN WATER AND STEAM, report, July 21, 1960; Richland, Washington. (digital.library.unt.edu/ark:/67531/metadc872551/: accessed December 11, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.