Determining local thermal transport in a composite uranium-nitride/silicide nuclear fuel using square-pulse transient thermoreflectance technique

Middlemas, Scott C; Hua, Zilong; Yorgason, William Tanner; Schley, Robert S; Khanolkar, Amey Rajendra; Khafizov, Marat; Hurley, David H

doi:10.1016/j.jnucmat.2019.151842

Title: Determining local thermal transport in a composite uranium-nitride/silicide nuclear fuel using square-pulse transient thermoreflectance technique

Journal Article · Sat Oct 12 00:00:00 EDT 2019 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2019.151842· OSTI ID:1642923

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^[1]; Yorgason, William Tanner ^[2];

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^[1]; Khafizov, Marat ^[3];

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Idaho National Lab. (INL), Idaho Falls, ID (United States)
Utah State Univ., Logan, UT (United States)
The Ohio State Univ., Columbus, OH (United States)

Laser-based techniques have become an appealing option for determining the thermal diffusivities (D) and conductivities (k) of nuclear materials that would otherwise prove too hazardous or difficult to measure otherwise. These techniques have enabled non-destructive and non-contact thermal transport measurements with micron-level spatial resolution. In this study, a new time-domain technique known as square-wave pulse thermoreflectance (SPTR) is described and used to determine D values of both uranium sesquisilicide (U₃Si₂) and uranium nitride (UN) phases in a composite fuel. An extensive sensitivity analysis was conducted that identified the optimal measurement parameters of standard materials with a range of thermal transport properties comparable to those of various fuel types. The standards were measured using both SPTR as well as a spatial-domain thermoreflectance technique (SDTR). Several U₃Si₂ and UN phase regions of polished UN/U₃Si₂ (70/30 vol.%) samples were measured using both methods, and the resulting calculated D and k values are reported, with both techniques showing excellent agreement between samples. Finally, the ability to use the technique for local diffusivity mapping was demonstrated over a multiphase region, and could be used to determine thermal transport properties in precipitates, secondary phases, and irradiation-damaged regions of post-irradiated fuel samples.

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Research Organization:: Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE), Fuel Cycle Technologies; USDOE Office of Nuclear Energy (NE), Fuel Cycle Technologies (NE-5)

Grant/Contract Number:: AC07-05ID14517

OSTI ID:: 1642923

Alternate ID(s):: OSTI ID: 1572569; OSTI ID: 1735523

Report Number(s):: INL-JOU-19-54759-Rev000; INL/CON-19-52657-Rev001; TRN: US2201951

Journal Information:: Journal of Nuclear Materials, Vol. 528; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Cited by: 6 works

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Title: Determining local thermal transport in a composite uranium-nitride/silicide nuclear fuel using square-pulse transient thermoreflectance technique

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