Qualification of sintered U O2 pellets. Vol. 3
Creators
- 1. Metallurgy Dept., Nuclear Research Center, Atomic Energy Authority, Cairo, (Egypt)
Description
The main objective of this work is to develop known procedures for fabrication and testing U O2 pellets starting from U O2 powder for producing experimental fuel elements. This paper concentrates on some quality parameters which are basic requirements for pellet qualification for use in nuclear reactors. This includes green and sintered pellet density, sintered pellet dimensions and grain size. Fabrication processes included pre-pressing, granulation, final automatic pressing and sintering (two regimes). The quality control of each fabrication step was planned, tested and verified. Experimental results are presented for about 100 pellets. These include green density, sintered density, pressing parameters and average grain size. These findings are statically evaluated and related to the fabrication conditions. 8 figs., 2 tabs
Files
28029532.pdf
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Additional details
Publishing Information
- Imprint Title
- Proceedings of the sixth conference of nuclear sciences and applications. Vol. 1-4
- Imprint Pagination
- 1760 p.
- Journal Page Range
- p. 396.
- Report number
- INIS-EG--002
Conference
- Title
- 6. conference on nuclear sciences and applications.
- Dates
- 15-20 Mar 1996.
- Place
- Cairo (Egypt).
INIS
- Country of Publication
- Egypt
- Country of Input or Organization
- Egypt
- INIS RN
- 28029532
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- DENSITY; EXPERIMENTAL DATA; FUEL ELEMENTS; FUEL PELLETS; GRAIN SIZE; POWDERS; REACTORS; SINTERED MATERIALS; URANIUM OXIDES
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; CRYSTAL STRUCTURE; DATA; INFORMATION; MATERIALS; MICROSTRUCTURE; NUMERICAL DATA; OXIDES; OXYGEN COMPOUNDS; PHYSICAL PROPERTIES; REACTOR COMPONENTS; SIZE; URANIUM COMPOUNDS