High Temperature Steam Corrosion of Cladding for Nuclear Applications: Experimental

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Stability of cladding materials under off-normal conditions is an important issue for the safe operation of light water nuclear reactors. Metals, ceramics, and metal/ceramic composites are being investigated as substitutes for traditional zirconium-based cladding. To support down-selection of these advanced materials and designs, a test apparatus was constructed to study the onset and evolution of cladding oxidation, and deformation behavior of cladding materials, under loss-of-coolant accident scenarios. Preliminary oxidation tests were conducted in dry oxygen and in saturated steam/air environments at 1000OC. Tube samples of Zr-702, Zr-702 reinforced with 1 ply of a ß-SiC CMC overbraid, and sintered a-SiC were ... continued below

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McHugh, Kevin M.; Garnier, John E.; Rashkeev, Sergey; Glazoff, Michael V.; Griffith, George W. & Bragg-Sitton, Shannong M. January 2013.

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Stability of cladding materials under off-normal conditions is an important issue for the safe operation of light water nuclear reactors. Metals, ceramics, and metal/ceramic composites are being investigated as substitutes for traditional zirconium-based cladding. To support down-selection of these advanced materials and designs, a test apparatus was constructed to study the onset and evolution of cladding oxidation, and deformation behavior of cladding materials, under loss-of-coolant accident scenarios. Preliminary oxidation tests were conducted in dry oxygen and in saturated steam/air environments at 1000OC. Tube samples of Zr-702, Zr-702 reinforced with 1 ply of a ß-SiC CMC overbraid, and sintered a-SiC were tested. Samples were induction heated by coupling to a molybdenum susceptor inside the tubes. The deformation behavior of He-pressurized tubes of Zr-702 and SiC CMC-reinforced Zr-702, heated to rupture, was also examined.

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  • 37th International Conference & Exposition on Advanced Ceramics & Composites (ICACC 2013),Daytona Beach, FL,01/27/2013,02/01/2013

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  • Report No.: INL/CON-13-28111
  • Grant Number: DE-AC07-05ID14517
  • Office of Scientific & Technical Information Report Number: 1076539
  • Archival Resource Key: ark:/67531/metadc830561

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  • January 2013

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  • May 19, 2016, 9:45 a.m.

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  • June 8, 2016, 4:01 p.m.

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McHugh, Kevin M.; Garnier, John E.; Rashkeev, Sergey; Glazoff, Michael V.; Griffith, George W. & Bragg-Sitton, Shannong M. High Temperature Steam Corrosion of Cladding for Nuclear Applications: Experimental, article, January 2013; Idaho Falls, Idaho. (digital.library.unt.edu/ark:/67531/metadc830561/: accessed December 14, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.