Thermophysical properties of high-density, sintered monoliths of yttrium dihydride in the range 373–773&nbsp;K

Shivprasad, Aditya Prahlad; Vogel, Sven C.; Mehta, Vedant Kiritkumar; Cooper, Michael William Donald; Saleh, Tarik A.; White, Joshua Taylor; Wermer, Joseph Raymond; Luther, Erik Paul; Trellue, Holly Renee

doi:10.1016/j.jallcom.2020.156303

Thermophysical properties of high-density, sintered monoliths of yttrium dihydride in the range 373–773 K

Journal Article · Thu Aug 13 00:00:00 EDT 2020 · Journal of Alloys and Compounds

DOI:https://doi.org/10.1016/j.jallcom.2020.156303· OSTI ID:1726208

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Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Georgia Inst. of Technology, Atlanta, GA (United States); Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

Yttrium dihydride is a promising nuclear reactor moderator for high-temperature, thermal micro-reactors due to its ability to retain hydrogen to high temperatures while having a relatively low impact on neutron economy. However, it is difficult to fabricate yttrium dihydride in high-density, near net-shape monoliths for moderator applications due to challenges associated with the hydrogen absorption process. Here, high-density monoliths of yttrium dihydride were prepared by powder metallurgical methods. The lattice strain and thermal expansion coefficient were measured using neutron diffraction of powders of directly-hydrided yttrium, while the molar heat capacity and thermal diffusivity of sintered yttrium dihydride were measured using differential scanning calorimetry (DSC) and laser flash analysis (LFA), respectively. The molar heat capacity of yttrium dihydride was also calculated using density functional theory (DFT) for comparison. These parameters were used to then calculate the thermal conductivity and resistivity of yttrium dihydride as a function of temperature. The thermophysical properties of materials produced by both methods were observed to be consistent with the values from literature for yttrium dihydride. Due to the novelty of producing yttrium dihydride by powder metallurgical methods, this result indicated that the sintered monoliths were of high quality and that powder metallurgy is a viable method for large-scale production of yttrium dihydride monoliths for nuclear reactor moderator applications.

View Accepted Manuscript (DOE)

Research Organization:: Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)

Sponsoring Organization:: USDOE Laboratory Directed Research and Development (LDRD) Program; USDOE National Nuclear Security Administration (NNSA); USDOE Office of Nuclear Energy (NE)

Grant/Contract Number:: 89233218CNA000001

OSTI ID:: 1726208

Alternate ID(s):: OSTI ID: 1656662

Report Number(s):: LA-UR--20-23935

Journal Information:: Journal of Alloys and Compounds, Journal Name: Journal of Alloys and Compounds Vol. 850; ISSN 0925-8388

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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