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Title: Enhanced thermal conductivity of spark plasma-sintered thorium dioxide-silicon carbide composite fuel pellets

Journal Article · · Nuclear Engineering and Technology

Thorium dioxide (ThO2)-silicon carbide (SiC) composite fuel pellets were fabricated via the spark plasma-sintering (SPS) method to investigate the role of the addition of SiC in enhancing the thermal conductivity of ThO2 fuel. SiC particles with an average size of 1μm in 10 and 15 vol% were used to manufacture the composite pellets. The changes in the composites' densification, microstructure and thermal conductivity were explored by comparing them with pure ThO2 pellets. The structural and microstructural characterization of the composite pellets has revealed that SPS could manufacture high-quality composite pellets without having any reaction products or intermetallic. The density measurement by the Archimedes principles and the grain size from the electron back-scattered diffraction (EBSD) analysis has indicated that the composites have higher densities and smaller grain sizes than the pellets without SiC addition. Finally, thermal conductivity as a function of temperature has revealed that sintered ThO2—SiC composites showed an increase of up to 56% in thermal conductivity compared to pristine ThO2 pellets.

Research Organization:
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Sponsoring Organization:
USDOE
Grant/Contract Number:
AC07- 05ID14517; AC07-05ID14517
OSTI ID:
1987427
Alternate ID(s):
OSTI ID: 2281386
Report Number(s):
INL/JOU-22-70326-Rev000; S1738573323003029; PII: S1738573323003029
Journal Information:
Nuclear Engineering and Technology, Journal Name: Nuclear Engineering and Technology Vol. 55 Journal Issue: 10; ISSN 1738-5733
Publisher:
ElsevierCopyright Statement
Country of Publication:
Korea, Republic of
Language:
English

References (28)

High temperature X-ray diffractometric studies on the lattice thermal expansion behaviour of UO2, ThO2 and (U0.2Th0.8)O2 doped with fission product oxides journal December 1991
Uranium dioxide - Molybdenum composite fuel pellets with enhanced thermal conductivity manufactured via spark plasma sintering journal September 2019
Thermal Energy Transport in Oxide Nuclear Fuel journal December 2021
Fabrication methods and thermal hydraulics analysis of enhanced thermal conductivity UO2–BeO fuel in light water reactors journal July 2015
High temperature thermal physical performance of BeO/UO2 composites prepared by spark plasma sintering (SPS) journal January 2018
Flash Method of Determining Thermal Diffusivity, Heat Capacity, and Thermal Conductivity journal September 1961
Adapting the deep burn in-core fuel management strategy for the gas turbine – modular helium reactor to a uranium–thorium fuel journal November 2005
Thermal diffusivity and conductivity of thorium- uranium mixed oxides journal March 2018
Evaluation of thermophysical properties of UO2-10 Vol% Mo nuclear fuel pellets journal February 2022
Thermally-Conductive and Mechanically-Robust Graphene Nanoplatelet Reinforced UO2 Composite Nuclear Fuels journal February 2018
Criticality investigations for the fixed bed nuclear reactor using thorium fuel mixed with plutonium or minor actinides journal August 2009
The influence of SiC particle size and volume fraction on the thermal conductivity of spark plasma sintered UO2–SiC composites journal November 2013
Alternative Applications of Homogeneous Thoria-Urania Fuel in Light Water Reactors to Enhance the Economics of the Thorium Fuel Cycle journal July 2004
Particle-type Burnable Poisons for Thorium-based Fuel in HTGR journal May 2015
Thermal conductivity of bulk and porous ThO2: Atomistic and experimental study journal August 2019
Enhanced Thermal Conductivity for LWR Fuel journal January 2010
Fully coupled multiphysics modeling of enhanced thermal conductivity UO 2 –BeO fuel performance in a light water reactor journal December 2015
Fabrication of Sintered Annular Fuel Pellet for HANARO Irradiation Test journal April 2010
Effect of silicon carbide addition on the microstructure, hardness and densification properties of spark plasma sintered Ni-Zn-Al alloy journal October 2019
Cost–benefit analysis of BeO–UO2 nuclear fuel journal November 2010
Enhanced thermal conductivity of uranium dioxide–silicon carbide composite fuel pellets prepared by Spark Plasma Sintering (SPS) journal February 2013
On the Densification Behavior of (0.2, 0.5, and 1 Wt Pct) CNT-YSZ Ceramic Composites Processed via Spark Plasma Sintering journal March 2015
Spark plasma sintering of diamond-reinforced uranium dioxide composite fuel pellets journal December 2015
Middle-term thorium strategy for PWR fleets journal December 2016
Thermal Conductivity of UO 2 -BeO Pellet journal February 1996
The Nonproliferative Light Water Thorium Reactor: A New Approach to Light Water Reactor Core Technology journal December 1998
The effect of SPS processing parameters on the microstructure and thermal conductivity of ThO2 journal December 2019
Influence of Carbon Nanotube Dispersion in UO 2 –Carbon Nanotube Ceramic Matrix Composites Utilizing Spark Plasma Sintering journal March 2015