Characterization of aluminum and boron carbide based additive manufactured material for thermal neutron shielding

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Abstract

We characterize the suitability of two additive manufactured materials for use in shielding thermal neutrons for neutron scattering instrumentation. We compare two different boron based additive manufactured masks to a traditionally manufactured boron nitride mask in a real-use case scenario. The first additive manufactured mask is a composite of aluminum and boron carbide. The second additive manufactured mask is a composite of boron carbide and cyanoacrylate. We report the thermal conductivity of the aluminum boron carbide mask in comparison to other relevant materials. The aluminum boron carbide material may find use in shielding applications where thermal conductivity, a low total neutron scattering cross section, and low toxicity are criteria.

Original languageEnglish
Article number112463
JournalMaterials and Design
Volume237
DOIs
StatePublished - Jan 2024

Funding

This manuscript has been authored by UT-Battelle, LLC under Contract No. DE-AC05-00OR22725 with the U.S. Department of Energy. The United States Government retains and the publisher, by accepting the article for publication, acknowledges that the United States Government retains a non-exclusive, paid-up, irrevocable, world-wide license to publish or reproduce the published form of this manuscript, or allow others to do so, for United States Government purposes. The Department of Energy will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (http://energy.gov/downloads/doe-public-access-plan).We acknowledge SBIR funding from DOE DE-SC0019721 and NASA 80NSSC21C0471. A portion of this research used resources at the Spallation Neutron Source, a DOE Office of Science User Facility operated by the Oak Ridge National Laboratory. Thermal conductivity measurements (A.F.M.) were supported by the U.S. Department of Energy, Office of Science, Basic Energy Sciences, Materials Sciences and Engineering Division. M. B. Stone acknowledges discussions regarding biological shielding with Scott Schwahn and discussions regarding CA-B4C with David Anderson. We acknowledge SBIR funding from DOE DE-SC0019721 and NASA 80NSSC21C0471 . A portion of this research used resources at the Spallation Neutron Source, a DOE Office of Science User Facility operated by the Oak Ridge National Laboratory. Thermal conductivity measurements (A.F.M.) were supported by the U.S. Department of Energy , Office of Science, Basic Energy Sciences, Materials Sciences and Engineering Division. M. B. Stone acknowledges discussions regarding biological shielding with Scott Schwahn and discussions regarding CA-B 4 C with David Anderson.

FundersFunder number
DOE Public Access Plan
United States Government
U.S. Department of EnergyDE-SC0019721
National Aeronautics and Space Administration80NSSC21C0471
Office of Science
Basic Energy Sciences
Oak Ridge National Laboratory
Small Business Innovation Research
Division of Materials Sciences and Engineering

    Keywords

    • Additive manufacturing
    • Neutron irradiation
    • Neutron scattering
    • Neutron shielding

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