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Structure–property relations in graphitic pebbles for nuclear applications

Journal Article · · Nuclear Engineering and Design

This work presents an analytical approach for holistically characterizing graphitic matrix pebbles for nuclear applications whereby the macrostructure, microstructure, and thermophysical properties of pebbles are determined. A systematic sectioning method was applied to several pebbles to describe the regional properties of the samples. Intact matrix-only spheres and sections of spheres fabricated by Kairos Power were characterized via optical imaging, x-ray computed tomography, x-ray diffraction, and ellipsometry to determine 2D and 3D macrostructure and anisotropy. The thermophysical properties of these materials were determined via measurements of density, specific heat, thermal expansion, and thermal diffusivity. The results of this study indicate that the pebble fabrication methods and their resultant effect on microstructure have a nontrivial effect on thermophysical properties, confirming the importance of robust characterization of these components. A discussion of the characterization approach and its applicability to nuclear fuel development activities is also included.

Research Organization:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE Office of Science (SC)
Grant/Contract Number:
AC05-00OR22725
OSTI ID:
1995678
Journal Information:
Nuclear Engineering and Design, Vol. 414, Issue 1; ISSN 0029-5493
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

References (21)

Multidimensional multiphysics simulation of nuclear fuel behavior journal April 2012
Fuel for pebble-bed HTRs journal April 1984
Automatic X-ray inspection for the HTR-PM spherical fuel elements journal December 2014
Effects of microstructure on the oxidation behavior of A3 matrix‐grade graphite journal September 2020
Determination of the specific heat capacity of a graphite sample using absolute and differential methods journal September 2007
Analysis of DR testing blind zone of spherical fuel elements for 10MW high-temperature gas-cooled reactor journal December 2013
Dimensional change, irradiation creep and thermal/mechanical property changes in nuclear graphite journal April 2016
Evaluation of pebble scanning strategies for fuel qualification by simple simulated radiography journal November 2021
Measurement of optical functions of highly oriented pyrolytic graphite in the visible journal August 2007
Thermal conductivity of polycrystalline graphite journal August 1968
Texture analysis of AGR program matrix materials journal November 2022
Determination of oxidation rates and volatile oxidation products for HTGR graphite matrix material exposed to steam atmospheres journal December 2021
Spherical fuel elements for advanced HTR manufacture and qualification by irradiation testing journal April 1990
FEA-aided investigation of the effective thermal conductivity in a medium with embedded spheres journal September 2021
Comparative analysis of microstructure and reactive sites for nuclear graphite IG-110 and graphite matrix A3 journal January 2020
Experimental measurement of thermal conductivity along different crystallographic planes in graphite journal July 2020
Coated particle fuel: Historical perspectives and current progress journal March 2019
Kinetic study of graphite oxidation along two lattice directions journal June 2005
Optical anisotropy measurements of TRISO nuclear fuel particle cross-sections: The method journal January 2008
Fabrication methods and anisotropic properties of graphite matrix compacts for use in HTGR journal February 2018
Qualification of HTR pebbles by X-ray tomography and thermal analysis journal October 2012