Uranium dioxide - Molybdenum composite fuel pellets with enhanced thermal conductivity manufactured via spark plasma sintering
Creators
- 1. Nuclear Fuels Centre of Excellence, School of Mechanical, Aerospace and Civil Engineering, The University of Manchester, Manchester, M13 9PL (United Kingdom)
Description
Highlights: • Successful manufacture of UO2–Mo composites using spark plasma sintering. • Thermal conductivity improvements achieved with modest Mo inclusions. • Development of dis-continuous Mo channels throughout UO2 microstructure. • High density composite fuel manufactured with short process times. - Abstract: Fuel for nuclear reactors with an increased thermal conductivity offers the potential for lower fuel operating temperatures and reduced fission gas release rates. Uranium dioxide (UO2) based composites could provide a method of achieving a higher thermal conductivity and molybdenum (Mo) has been identified as a potential candidate for use in such composites. Uranium dioxide composites containing Mo were manufactured via spark plasma sintering with concentrations of up to 10 vol% Mo. The composites were characterised on their microstructural properties and the thermal conductivity was determined by laser flash analysis. The composites achieved densities greater than 95 %TD but lower than typical grain size. The microstructure contained channel like structures of Mo, due to the use of an agglomerated UO2 precursor powder. An increased thermal conductivity, proportional to the concentration of Mo, was determined for the composites. At the maximum measurement temperature of 800 ∘ C the increase was found to be 65% and 117% in the 5 and 10 vol% composites respectively.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.jnucmat.2019.05.059Additional details
Identifiers
- DOI
- 10.1016/j.jnucmat.2019.05.059;
- PII
- S0022311518315046;
Publishing Information
- Journal Title
- Journal of Nuclear Materials
- Journal Volume
- 523
- Journal Page Range
- p. 360-368
- ISSN
- 0022-3115
- CODEN
- JNUMAM
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 51048849
- Subject category
- S36: MATERIALS SCIENCE;
- Descriptors DEI
- ACCIDENT-TOLERANT NUCLEAR FUELS; FISSION PRODUCT RELEASE; FUEL PELLETS; GRAIN SIZE; MOLYBDENUM; PLASMA; SINTERING; THERMAL CONDUCTIVITY; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; ELEMENTS; ENERGY SOURCES; FABRICATION; FUELS; MATERIALS; METALS; MICROSTRUCTURE; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; PELLETS; PHYSICAL PROPERTIES; REACTOR MATERIALS; REFRACTORY METALS; SIZE; THERMODYNAMIC PROPERTIES; TRANSITION ELEMENTS; URANIUM COMPOUNDS; URANIUM OXIDES
Optional Information
- Notes
- Crown Copyright © 2019 Published by Elsevier B.V.