Journal of Nuclear Materials
ISSN: 0022-3115
Datasets associated with articles published in Journal of Nuclear Materials
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- Data for: The influence of transition metal solutes on the dissolution and diffusion of oxygen in tungstenFigure 2 The binding energies of the TM solute with an oxygen atom in their {\rm Oct}_{1nn} and {\rm Tet}_{1nn} to {\rm Tet}_{7nn} sites as displayed in Fig. 1. Figure 3 The volume change of the supercell, respectively, caused by the substitutional TM solutes, interstitial oxygen at Tet site and Sol-O pair with oxygen located at the 1nn and 2nn shells. Figure 4 The fraction of oxygen around the solute atom in the 1nn ∼ 5nn shells and the f_\infty at a given concentration of the TM solute and oxygen (10-4 and 10-5, respectively) as a function of temperature. The red line represents the fraction of oxygen in the pure tungsten. Figure 5 The effective diffusivity of oxygen in the W-TM solid solution with the TM solute concentration 10-4. (For an interpretation of the references to colour in this figure legend, the reader is referred to the web version of this article). Figure 61 (b) The energy difference when the oxygen atom is located nearby {\rm Oct}_{near} and {\rm Oct}_{far}. (c) The total binding energies of the Sol-Vac-O complexes, E_b^{Sol,Vac,O}. (d) The incremental binding energies between the oxygen atom and the Sol-Vac pair, E_b^{O,Sol-Vac}. (e) The incremental binding energies between the TM soulte atom and the Vac-O pair, E_b^{Sol,Vac-O}, and the binding energies between the TM solute and the vacancy, E_b^{Sol,Vac}.
- Data for: A threshold density of helium bubbles induces a ductile-to-brittle transition at a grain boundary in nickelThis file contains a nickel-helium (Ni-He) embedded atom method (EAM) potential.
- Data for: Morphological characterization of the fresh ZrN coated UMo powders used in EMPIrE irradiation experiment: a practical approach. Supplementary Information on the powder characterization of UMo(ZrN) particles
- Data for: Thermodynamic modeling of Y-H and Y-Zr-H system aided by first-principles and its application in bulk hydride moderator fabricationThermodynamic database of Y-H system
- Data for: A logical approach for zero-rupture Fully Ceramic Microencapsulated (FCM) fuelsSupporting spatial determination of particle positions
- Data for: Thermal Conductivity of Uranium Metal and Uranium-Zirconium Alloys Fabricated via Powder MetallurgyThermal diffusivity data of uranium, uranium 5 mass% zirconium, and uranium 5 mass% zirconium. Data collected from a Netzsch 447 from 20C to 300C using the Cape Lehman model with pulse correction. Solid samples and samples with porosity up to approximately 70% are included.
- Data for: Synthesis and characterization of iron phosphate based glass-ceramics containing sodium zirconium phosphate phase for nuclear waste immobilizationRaw data and processed data for the manuscript.
- Data for: Tensile Property Prediction by Feature Engineering Guided Machine Learning in Reduced Activation Ferritic/Martensitic Steelsthe original dataset from references and the modified dataset for the mechanical properties of RAFM steels
- Data for: Study of Entrainment of Li2O in Product from Direct Electrolytic Reduction of UO2 in Molten LiCl-Li2O. Part 1: Post-Processing and Analysis TechniquesThis data is from the electrolytic oxide reduction of uranium oxide in LiCl-Li2O at 650 C. The goal of these tests were to elucidate Li2O entrainment behavior with respect to changes in process variables. Several reductions and associated characterizations are contained including titration, TGA, and SEM data.
- Data for: Synthesis of phosphate based glass-ceramic waste forms by a melt-quenching process: The formation processData for: Synthesis of phosphate based glass-ceramic waste forms by a melt-quenching process: The formation process