科技报告详细信息
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 |
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美国|英语 | |
来源: SciTech Connect | |
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【 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.
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