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7094 file(s)Microstructural characterization of nuclear graphite provides insight into the constituent phases (filler, binder, and void content) and material features across multiple length...
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The Foundations of Irradiation Testing 2026 workshop provided an introduction to the fundamentals of irradiation testing, radiation damage, nuclear fuels, structural materials,...
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Bashforth and Adams (1883) published solutions to the Young–Laplace equation governing axi symmetric capillary surfaces, providing tabulated dimensionless profile coordinates...
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The 2026 Nuclear Science User Facilities Users Organization meeting was held in association with the Minerals, Metals and Materials Society (TMS) 2026 Annual Meeting and...
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16 file(s)The 2024 Nuclear Science User Facilities Users Organization meeting was held in association with the Minerals, Metals and Materials Society (TMS) 2024 Annual Meeting and...
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40 file(s)The 2025 Nuclear Science User Facilities Annual Program Review was held in at INL on May 2025
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43 file(s)The 2026 Nuclear Science User Facilities Annual Program Review was held in at INL on May 11, 2026
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This dataset contains synchrotron micro–X-ray computed tomography (micro-XCT) image stacks of dental enamel from multiple mammalian species, including lion, wolf, wild African...
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Synchrotron X-ray computed tomography data of mammalian enamel from the Advanced Photon Source (nano XCT) and Advanced Light Source (micro XCT). The raw, as well as processed,...
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510 file(s)The objective of this study is to understand the effect of Phosphorous (P) on precipitation and segregation behavior in neutron irradiated Reactor Pressure Vessel steels in the...
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3071 file(s)Primary Coolant Apparatus Test (PCAT) for the Microreactor Applications Research Validation (MARVEL) project. The PCAT replicates the MARVEL reactor’s primary loop . PCAT uses...
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Radiation-Induced Surface Activation is an inherent phenomenon where surfaces that are exposed to gamma irradiation are observed to undergo an increase in wettability. This...
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A thorough understanding of oxidation is important when considering the health and integrity of graphite components in graphite reactors. For the next generation of graphite...
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Ultrasonic technologies offer the potential for high accuracy and resolution in-pile measurement of a range of parameters, including geometry changes, temperature, crack...
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Oxide dispersion strengthened (ODS) alloys are promising candidate materials for the next generation advanced nuclear reactors due to their superior irradiation resistance and...
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What determines precipitate morphologies in co-precipitating alloy systems? We focus on alloys of two precipitating phases, with the fast-precipitating phase acting as...
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Several Department of Energy Office of Nuclear Energy (DOE-NE) programs, such as the Fuel Cycle Research and Development (FCRD), Advanced Reactor Concepts (ARC), Light Water...
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Particles comprised of a thermal neutron absorbing material (HfAl3) are dispersed in a metal matrix material with high thermal conductivity (aluminum) to conduct the heat...
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Given a growing interest in uranium salts for pyrochemical processing of used fuel and uranium-fueled molten salt reactors, the synthesis of uranium trichloride in alkali-metal...
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The effects of neutron irradiation on microstructural evolution and the resultant changes in physical and mechanical properties are of critical importance for the development of...