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

Technical Report ·
DOI:https://doi.org/10.2172/1463514· OSTI ID:1463514
 [1];  [1]
  1. Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

This report presents a historical overview of stress corrosion cracking (SCC) in uranium-molybdenum alloys, focusing primarily on U-10 wt. pct. Mo (U-10Mo). 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. One disadvantage of U-10Mo is its propensity towards stress corrosion cracking (SCC), driven by high residual stresses resulting from its high yield strength. This report contains a metallurgical overview of U-10Mo alloys incorporating processing, microstructural evolution, and mechanical properties. This report also summarizes SCC literature including contributing factors, initiation and propagation, the mechanism responsible for U-10Mo SCC, and possible solutions to the problem. A brief synopsis of interviews with key personnel from several Department of Energy (DOE) facilities and BWX Technologies (BWXT) is also included. Recommendations for future studies are outlined.

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:
1463514
Report Number(s):
LA-UR-18-25767; TRN: US1901770
Country of Publication:
United States
Language:
English