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

Abstract

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.

Authors:
ORCiD logo [1]; ORCiD logo [1];  [2]
  1. Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
  2. Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
Publication Date:
Research Org.:
Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Sponsoring Org.:
USDOE National Nuclear Security Administration (NNSA)
OSTI Identifier:
1481958
Report Number(s):
LA-UR-18-28445
DOE Contract Number:  
AC52-06NA25396
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English

Citation Formats

Hill, Mary Ann, Lawrence, Samantha Kay, and Henager, Jr., Charles H. Historical Review of Stress Corrosion Cracking in Concentrated Uranium-Molybdenum Alloys. United States: N. p., 2018. Web. doi:10.2172/1481958.
Hill, Mary Ann, Lawrence, Samantha Kay, & Henager, Jr., Charles H. Historical Review of Stress Corrosion Cracking in Concentrated Uranium-Molybdenum Alloys. United States. doi:10.2172/1481958.
Hill, Mary Ann, Lawrence, Samantha Kay, and Henager, Jr., Charles H. Thu . "Historical Review of Stress Corrosion Cracking in Concentrated Uranium-Molybdenum Alloys". United States. doi:10.2172/1481958. https://www.osti.gov/servlets/purl/1481958.
@article{osti_1481958,
title = {Historical Review of Stress Corrosion Cracking in Concentrated Uranium-Molybdenum Alloys},
author = {Hill, Mary Ann and Lawrence, Samantha Kay and Henager, Jr., Charles H.},
abstractNote = {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.},
doi = {10.2172/1481958},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2018},
month = {11}
}

Technical Report:

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