Report on Characterization of U-10 wt.% Zr Alloy

McKeown, J ; Wall, M ; Hsiung, L ; Turchi, P

关键词: ALLOYS;    HEAT TREATMENTS;    LAWRENCE LIVERMORE NATIONAL LABORATORY;    METALLOGRAPHY;    NUCLEAR FUELS;   

DOI  :  10.2172/1037838
RP-ID  :  LLNL-TR-534973
PID  :  OSTI ID: 1037838
Others  :  TRN: US1201764

美国|英语

来源: SciTech Connect

【 摘 要 】

This report summarizes the chemical and structural characterization results for a U-10 wt.% Zr alloy to be used in an ultra-high burn-up nuclear fuel concept. The as-cast alloy material was received from Texas A and M University. Characterization and an initial heat treatment of the alloy material were conducted at Lawrence Livermore National Laboratory. The as-received ingot was sectioned for X-ray analysis, metallography, SEM, TEM, and heat treatments, as shown in Figure 1.