Thermal conductivity reduction in (Zr 0.25 Ta 0.25 Nb 0.25 Ti 0.25 )C high entropy carbide from extrinsic lattice defects
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36 MATERIALS SCIENCE↗
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Thermal Conductivity Measurements on Irradiated TRISO Fuel at IMCL
INL is leading the development and testing of accident tolerant fuels: fuels that resist melting down and that contain radioactive byproducts, preventing their release into their environment. One such fuel, called TRi-structural ISOtropic particle fuel (TRISO) See Fig 1. Understanding how heat propagates through a fuel is essential to fuel development and qualification. When irradiated in a reactor the properties that affect heat transport change. Our objective is to quantify the change in thermal properties of TRISO after irradiation.
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
Anisotropic thermal conductivity tensor of β-Y2Si2O7 for orientational control of heat flow on micrometer scales
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Olson, David H. (ORCID:0000000223261102)↗
The role of impurities and degradation on the thermal conductivity of carbon fiber and amorphous carbon
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Konnik, Matthew T.↗
Deep material network for thermal conductivity problems: Application to woven composites
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Shin, Dongil (ORCID:0000000336180624)↗
Transient multilayer analytical model of a line heat source probe for in-pile thermal conductivity measurements
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Wada, Katelyn (ORCID:0000000169596699)↗
Combined ab-initio and empirical model for irradiated metal alloys with a focus on uranium alloy fuel thermal conductivity
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Zhou, Shuxiang (ORCID:0000000250291251)↗
An ab-initio based semi-empirical thermal conductivity model for multiphase uranium-zirconium alloys
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Zhou, Shuxiang (ORCID:0000000250291251)↗