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Showing 1 to 12 of 12 for “"Zirconium hydride"”.
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Thermal analysis of uranium zirconium hydride fuel using a lead-bismuth gap at LWR operating temperatures
… advanced light water reactors (LWRs) is uranium zirconium hydride (UZH), a fuel currently being used in the popular TRIGA research reactors. UZH is being considered because unlike the current fuel of choice, uranium dioxide, it is metal based and therefore better able to transfer the heat out of …
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Influence of zirconium hydride on the biaxial creep behavior of Zircaloy-4 cladding for interim dry storage of spent nuclear fuel
Submission published under a 24 month embargo labeled 'U of I Access', the embargo will last until 2019-12-01
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Neutronic-Thermal Simulation of Micro Reactor Designs for the Purpose of Analyzing the Impact of Thermal Expansion and Hydrogen Migration in Metal Hydride Moderator
… this, by adding thermal expansion and zirconium hydride-based hydrogen diffusion to the neutronic-thermal simulation of multiple heat pipe microreactor designs. Microreactors’ smaller cores are inherently characterized by more leakage than gigawatt-scale reactor cores. The inclusion of …
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Investigation of the mechanical behavior of rim/blister structure hydride phases in Zircaloy-4 by utilizing high energy synchrotron X-ray diffraction
… problematic. One issue is the delayed hydride cracking (DHC) phenomenon which occurs during storage of used nuclear fuel (UNF). DHC is a time-dependent subcritical crack growth mechanism that can be induced by tensile stress hoop stress within the fuel cladding, even when this hoop …
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Radiation Effects on Thermal Properties of Advanced Nuclear Materials
… in high-flux neutron and gamma environments. Zirconium hydride (ZrH) and yttrium hydride (YH) have emerged as promising neutron moderating materials due to their exceptional hydrogen density leading to superior moderating power. Yet, the radiation-induced microstructural evolution and its …
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Effects of hydrogen uptake and yttrium doping on the oxidation of zirconium-yttrium alloys
Zirconium-based fuel cladding used in nuclear reactors is susceptible to significant hydrogen uptake during normal operating conditions. This results in the formation of zirconium hydride. The nucleation of a brittle hydride phase results in a degradation of cladding mechanical properties in the …
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Microstructure-informed modeling of hydrogen diffusion in zirconium polycrystals
Zirconium alloys are widely used in the core of various types of nuclear reactors. During service, the hot water coolant reacts with zirconium and releases hydrogen atoms that ingress into the lattice of the metal alloy. With time, hydrogen concentration exceeds its terminal solid solubility limit …
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Nuclear Electric Propulsion with Low Enriched Uranium
… order to make a fair comparison between them. A zirconium hydride moderator is found to be sub-optimal for an LEU system, with a larger but higher-temperature graphite-based core leading to an overall 40% lighter power system. This system was found to have a mass 50% greater than the best …
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Hydrogen Distribution in Metal Hydrides and its Effect on Reactor Physics Calculations
… scattering is explored, as it pertains to metal hydrides. Exciting and de-exciting vibrations corresponds to energy change, where a neutron may deposit energy into the material, thus inciting a vibration (phonon), or gain energy by destroying a phonon. This change in energy specifies inelastic …
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Investigation effect of external stress on hydrogen solvus in a zircaloy-4 fuel cladding alloy: application of in situ diffraction technique and mesoscale phase-field simulation
… reactors (LWRs). However, the formation of the zirconium hydride phase in the cladding significantly degrades its mechanical properties by reducing the local ductility and initiating crack propagation. Therefore, one of the current fuel performance modeling efforts is to simulate the degradation …
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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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Predicting the Influence of Hydrogen on Zirconium
… corrosion process that ensues when the alloys of zirconium used as structural components and fuel claddings in nuclear reactors react with the heavy water used as coolant in the CANDU® reactors results in the production of hydrogen or deuterium. Some of this hydrogen enters the alloy and causes a …