In-situ fabrication of dispersion nuclear fuel pellets with a core-shell structure
Creators
- 1. Department of Engineering and Applied Physics, University of Science and Technology of China, Huang-Shan Road, He-Fei (China)
Description
Highlights: • The fuel pellet with a core-shell structure was designed by an in-situ process. • The relationship between the shell thickness and mixing parameters were studied. • An empirical formula for the shell thickness and mixing parameters was established. - Abstract: Using the segregation phenomenon of different materials in the mixing process, the dispersion nuclear fuel pellet with a core-shell structure was firstly designed and fabricated by an in-situ preparation process. This core-shell structure could prevent the metal matrix from reacting with water to generate hydrogen, which improves the safety property of the pellet. Furthermore, it provides a perspective on integrated manufacture of pellets and claddings by one-step preparation. Effects of mixing process parameters on the shell thickness were investigated in detail. The results indicate that: a three-quarter cycle sinusoid could be used to describe the change in shell thickness with rotational speed; and there is a negative linear relationship between shell thickness and volume percentage of ZrO2 microspheres; the shell thickness increases as the particle size difference of ZrO2 microspheres/glass beads increases. What's more, an empirical formula describing the relationship between the shell thickness and these parameters has been established.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2019.06.028Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2019.06.028;
- PII
- S0306454919303469;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 134
- Journal Page Range
- p. 258-262
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 51007899
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- CLADDING; DISPERSION NUCLEAR FUELS; FABRICATION; FUEL PELLETS; GLASS; INTERSTITIAL HYDROGEN GENERATION; MATRIX MATERIALS; MICROSPHERES; SAFETY; ZIRCONIUM OXIDES
- Descriptors DEC
- CHALCOGENIDES; DEPOSITION; ENERGY SOURCES; FUELS; MATERIALS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; PELLETS; PHYSICAL RADIATION EFFECTS; RADIATION EFFECTS; REACTOR MATERIALS; SOLID FUELS; SURFACE COATING; TRANSITION ELEMENT COMPOUNDS; ZIRCONIUM COMPOUNDS
Optional Information
- Notes
- © 2019 Elsevier Ltd. All rights reserved.