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View article: In-Situ TEM study of microstructural evolution in proton irradiated single crystal UO2 under high-temperature annealing
In-Situ TEM study of microstructural evolution in proton irradiated single crystal UO2 under high-temperature annealing Open
Understanding microstructural changes in nuclear fuels under different irradiation conditions is important as it directly affects thermal, oxidation and mechanical properties and thereby reactor safety and longevity. This work focuses on t…
View article: Traveling Molten Zone Refining Process Development for Innovative Fuel Cycle Solutions
Traveling Molten Zone Refining Process Development for Innovative Fuel Cycle Solutions Open
Considering the phase diagrams of metallic spent fuel constituents, the melting and solidifying of spent metallic fuel causes three immiscible layers (actinide-rich, lanthanide-rich, and Group II-rich) and the condensate phase (Group I) to…
View article: Fabrication and Characterization of Candidate Alloys for Advanced LEU Fuel Concepts
Fabrication and Characterization of Candidate Alloys for Advanced LEU Fuel Concepts Open
A set of novel uranium-based alloys has been proposed for use in advanced LEU fuel systems. This study seeks to develop methods to fabricate single-phase alloys and evaluate the compatibilities of the alloys for use in composite fuel syste…
View article: Full Field Reconstruction and Uncertainty Quantification of Particle Image Velocimetry Measurements in A 5X5 Rod Bundle with Mixing Vane Spacer Grids
Full Field Reconstruction and Uncertainty Quantification of Particle Image Velocimetry Measurements in A 5X5 Rod Bundle with Mixing Vane Spacer Grids Open
One of the most commonly used methods for quantifying fluid velocity profiles is particle image velocimetry (PIV). This non-invasive measurement technique employs seeding particles in a transparent simulant fluid flowing through a geometry…
View article: Pressure Measurements in a Wire-Wrapped 61-Pin Hexagonal Fuel Bundle
Pressure Measurements in a Wire-Wrapped 61-Pin Hexagonal Fuel Bundle Open
To achieve longer-life liquid-metal fast reactor cores, designers are considering to increase the wall gap of the wire-wrapped hexagonal fuel bundles to account for volumetric void swelling and radiation creep. A new wire-wrapped hexagonal…
View article: Quantification of Boric Acid Concentration and Losses due to Vaporization in the PASTA Facility
Quantification of Boric Acid Concentration and Losses due to Vaporization in the PASTA Facility Open
During a loss of coolant accident in a pressurized water reactor, borated water is injected into the core through emergency core cooling system to reduce the decay heat, remove excess reactivity, and maintain an adequate core cooling throu…