Preparation of porous U-10%Mo alloy by powder metallurgy and its microstructure characterization
- 1. Science and Technology on Surface Physics and Chemistry Laboratory, Mianyang (China)
- 2. China Academy of Engineering Physics, Mianyang (China)
Description
U-Mo alloy is one of candidates of metallic fuel for advanced nuclear reactor due to its good irradiation behavior. Reasonably analysis suggests that the irradiation swell of U-Mo alloy can be decreased by introducing homogeneously distributed voids, because they can accommodate gaseous fission products. The process of preparing low density U-Mo alloy by powder metallurgy was described, including preparing low density bulk materials by pressing and vacuum sintering. A serial of U-10%Mo alloys with different densities were obtained and the microstructure was analyzed by optical microscopy (OM) and scanning electron microscopy (SEM). It is proved that the density of sample increases with sinister time under 1100℃. The void ratio can be controlled by adjusting sinister process conveniently. (authors)
Additional details
Publishing Information
- Journal Title
- Atomic Energy Science and Technology
- Journal Volume
- 47
- Journal Issue
- 2
- Journal Page Range
- p. 295-298
- ISSN
- 1000-6931
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 46131980
- Subject category
- S36: MATERIALS SCIENCE; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- DENSITY; FISSION PRODUCTS; IRRADIATION; MICROSTRUCTURE; NUCLEAR FUELS; OPTICAL MICROSCOPY; POROUS MATERIALS; POWDER METALLURGY; PRESSING; REACTORS; SCANNING ELECTRON MICROSCOPY; SINTERING; URANIUM-MOLYBDENUM FUELS; VOIDS
- Descriptors DEC
- ALLOY NUCLEAR FUELS; ELECTRON MICROSCOPY; ENERGY SOURCES; FABRICATION; FUELS; ISOTOPES; MATERIALS; MATERIALS WORKING; METALLURGY; MICROSCOPY; NUCLEAR FUELS; PHYSICAL PROPERTIES; RADIOACTIVE MATERIALS; REACTOR MATERIALS; SOLID FUELS
Optional Information
- Notes
- 3 figs., 3 tabs., 7 refs.