Historical Review of Stress Corrosion Cracking in Concentrated Uranium-Molybdenum Alloys

Technical Report · Thu Nov 08 00:00:00 EST 2018

DOI:https://doi.org/10.2172/1481958· OSTI ID:1481958

Hill, Mary Ann  ^[1]; Lawrence, Samantha Kay  ^[1]; Henager, Jr., Charles H. ^[2]

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1. Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
2. Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

This report presents a historical overview of stress corrosion cracking (SCC) in uranium-molybdenum alloys, focusing primarily on bare U-10 wt. pct. Mo (U-10Mo). The fuel system being pursued by the United States High Performance Research Reactor (USHPRR) project incorporates a zirconium interlayer applied early in the process which likely serves as a protective coating. This alloy has been chosen as the high density uranium monolithic fuel for converting research reactors from high enriched uranium (HEU) to low enriched uranium (LEU) fuel for its combination of fuel density and gamma phase stability.

• Research Organization: Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA)
• DOE Contract Number: AC52-06NA25396
• OSTI ID: 1481958
• Report Number(s): LA-UR-18-28445
• Country of Publication: United States
• Language: English