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Showing 1 to 14 of 14 for “"Zirconium Carbide"”.
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Coating Parameters of Zirconium Carbide On Advanced Triso Fuels
… characteristics and retention ability of silicon carbide as the main barrier against metallic fission products. This work investigates the deposition parameters necessary to create advanced TRISO particles consisting of the standard SiC TRISO coatings with an additional layer of ZrC applied …
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Microstructural evolution of zirconium carbide (ZrCₓ) ceramics under irradiation conditions
… of the microstructural evolution of Zirconium Carbide (ZrC<sub>2</sub>) ceramics under irradiation conditions is required for their successful implementation in advanced Gen-IV gas-cooled nuclear reactors. The research presented in this dissertation focusses on elucidating the ion and …
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The Effect of Coating Parameters On Advanced TRISO Fuels With Zirconium Carbide
<p>Recent studies of TRISO fuel behavior have shown a number of problems with the conventional SiC TRISO coating system at very high temperature, not unlike the temperatures obtainable in the very high temperature reactor (VHTR) design. These problems include but are not limited to over …
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Multiscale corrosion of zirconium carbide, carbon, and CF/ZRC under extreme environments
… thermal protection system materials, including zirconium carbide (ZrC), disordered carbons, and carbon fiber/zirconium carbide (Cf/ZrC) composites. Initial analysis focused on the ultra-high temperature oxidation behavior of hot-pressed substoichiometric zirconium carbide in a highly controlled …
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Characterization of Uranium Carbide Microspheres In An Inert Zirconium Carbide Matrix For Gas Fast Reactors
… of a dispersion/composite fuel involving Uranium Carbide (UC) and Zirconium Carbide (ZrC) have been characterized and studied. Uranium carbide (UC) microspheres produced in the USC-Nuclear Materials Laboratory were subjected to metallographic techniques, and then characterized by analytical …
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Non-stoichiometry and radiation damage effects in zirconium carbide and layered carbide ceramics for nuclear fuel cladding applications
Sub-stoichiometric Zirconium Carbide (ZrC) is a viable candidate for use in nuclear environments as it has shown desirable thermo-physical properties and an ability to tolerate radiation damage. These thermophysical properties, in some cases, are sensitive to stoichiometry making ZrC a customisable …
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Analysis of U-Zr-C-O Quaternary System for Applications in Advanced ZRC Coated Triso Particles
… thermogravimetric testing with both carbon and zirconium carbide powders to evaluate the efficiency of ZrC for usage as an oxygen getter in oxide TRISO fuels.</p>
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Thermodynamic and Thermochemical Investigation of Advanced Triso Coated Particle Fuels
… has been considered since the 1940s and the zirconium carbide layer of the advanced coated particle fuel has been considered to solve the specific problems such as overpressurization, kernel swelling, kernel migration, and/or attack of fission products since the 1970s. Thermochemical modeling …
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Synthesis, characterization, and properties of carbide dispersion-strengthened tungsten alloys for use as a plasma-facing material in nuclear fusion reactors
… by microalloying tungsten with transition metal carbides that capture the oxygen atoms, the impurity distribution can be altered to beneficially impact the mechanical properties. Through the advent of advanced powder processing techniques such as Spark plasma sintering, dense, fine-grained …
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Sintering techniques for microstructure control in ceramics
… were examined in two classes of materials; zirconium diboride ultra high temperature ceramic composites, and all solid lithium-ion battery phosphate materials. ^ Investigation of zirconium diboride ceramics focused on the effects of zirconium carbide as a secondary or tertiary phase in …
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The Deposition Characteristics of Zrc On Uo2 Kernels Produced For Advanced Triso Fuels In Gen-Iv Reactors
… operation and accident scenarios. The silicon carbide (SiC) layer typical of most TRISO fuels acts as both a diffusion barrier and a pressure vessel for the fuel. This research focuses on the development of an advanced TRISO particle in which zirconium carbide (ZrC) layer is placed directly on …
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Deciphering the role of dispersoids in dispersion-strengthened tungsten alloys on the mechanical properties and irradiation- driven response under nuclear fusion reactor-relevant conditions
… by microalloying tungsten with transition metal carbides that capture the oxygen atoms, the impurity distribution can be altered to beneficially impact the mechanical properties. Additionally, altering the interface concentration and type can increase the irradiation tolerance of tungsten. …
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Understanding How Tape Casting Titanium Diboride Shifts its Processing-Microstructure-Properties Paradigm Toward New Applications
… heat treatment at 2000°C of MOF PCN-222 produces zirconium carbide (ZrC) within a highly anisotropic particle. The resulting rod-shaped, glass-like carbon matrix embedded with ZrC crystals is described. These rods have potential as reinforcements for iii high temperature applications and as a …