Abstract: An integrated acoustic detection and rock direct tensile test machine includes a support frame. A top of the support frame is provided with a top plate and a bearing plate is provided above the top plate. The bearing plate is provided with force transferring rods, lower ends of which are provided with a tensile base. A top of the tensile base is provided with a lower clamp holder and a bottom of the top plate is provided with an upper clamp holder. An upper channel is provided inside the upper clamp holder. The upper channel is provided with an acoustic transmitting probe. A lower channel is provided inside the lower clamp holder. One end of the lower channel is communicated with the outside, the other end is provided with an acoustic receiving probe. The lower channel extends to a bottom of a clamping chamber of the lower clamp holder.

Abstract: A rock direct tensile test platform suitable for all material test machines includes a support frame. A top of the support frame is fixed with a top plate, and a bearing plate is provided above the top plate. The bearing plate is provided with a plurality of vertical force transferring rods. The force transferring rods vertically penetrate through the top plate and have a sliding fit with the top plate. Lower ends of the force transferring rods are provided with a tensile base. A top of the tensile base is provided with a lower clamp holder. A bottom of the top plate is provided with an upper clamp holder, and a clamp center of the upper clamp holder coincides with a clamp center of the lower clamp holder.

Abstract: A direct tensile and acoustic testing machine under rock seepage includes a sample and a support frame. A top of the support frame is fixed with a top plate, a bearing plate is provided above the top plate, the bearing plate is provided with a plurality of vertical force transferring rods, the force transferring rods vertically penetrate through the top plate and sliding fit with the top plate, lower ends of the force transferring rods are provided with a tensile base, a top of the tensile base is provided with a lower clamp holder, a bottom of the top plate is provided with an upper clamp holder, and a clamp center of the upper clamp holder overlaps with a clamp center of the lower clamp holder. An acoustic component and a seepage component are provided in the upper clamp holder and the lower clamp holder.

Abstract: Provided are a display panel and a manufacturing method thereof, and a display device. The display panel includes a base substrate and a plurality of sub-pixels. At least one sub-pixel includes a light-emitting element; a first transistor; a capacitor including a first electrode and a second electrode plate; a second transistor including a second active layer including a third and a fourth electrode area, and a second channel area; and a third transistor including a third active layer, and a third gate electrode connected to a reset line, the third active layer including a fifth electrode area, a sixth electrode area directly connected to an initialization line via a via hole, and a third channel area. An orthographic projection of the initialization line on the base substrate is located between orthographic projections of the reset line and the gate line on the base substrate.

Abstract: A method of forming a water resistant boundary on a fissile material for use in a water cooled nuclear reactor is described. The method comprises mixing a powdered fissile material selected from the group consisting of UN and U3Si2 with an additive selected from oxidation resistant materials having a melting or softening point lower than the sintering temperature of the fissile material, pressing the mixed fissile and additive materials into a pellet, sintering the pellet to a temperature greater than the melting point of the additive. Alternatively, if the melting point of the oxidation resistant particles is greater than the sintering temperature of UN or U3Si2, then the oxidation resistant particles can have a particle size distribution less than that of the UN or U3Si2.

Abstract: Disclosed herein is a method comprising coating a fissile, uranium-containing ceramic material with a water-resistant layer, the layer being non-reactive with the fissile, uranium-containing ceramic material. The coating is applied to a surface of the fissile, uranium-containing ceramic material. Also disclosed is a fuel for use in a nuclear reactor.

Abstract: A flexible display panel. The flexible display panel includes: a flexible substrate; a display element arranged on the flexible substrate; and a packaging layer covering the display element, the packaging layer including an inorganic thin film and an organic thin film that are stacked alternately, in which two protrusion structures that are engaged with each other are arranged between at least two adjacent thin films of the packaging layer.

Abstract: An improvement in a nuclear fuel rod is disclosed. The improved fuel rod includes a cladding tube, a plurality of fuel pellets stacked within the cladding tube, and a liquid material filling the gap between the fuel pellets and the cladding tube. The liquid material is selected from those having a thermal conductivity higher than that of helium, a melting point lower than about 400° C., a boiling point higher than 1600° C., and which are capable of wetting both the fuel pellets and the cladding sufficient to form a protective layer over the pellets and to wick into openings that may form in the cladding.

Abstract: A method of forming a water resistant boundary on a fissile material for use in a water cooled nuclear reactor is described. The method comprises mixing a powdered fissile material selected from the group consisting of UN and U3Si2 with an additive selected from oxidation resistant materials having a melting or softening point lower than the sintering temperature of the fissile material, pressing the mixed fissile and additive materials into a pellet, sintering the pellet to a temperature greater than the melting point of the additive.

Abstract: A method of forming a water resistant boundary on a fissile material for use in a water cooled nuclear reactor is described. The method comprises mixing a powdered fissile material selected from the group consisting of UN and U3Si2 with an additive selected from oxidation resistant materials having a melting or softening point lower than the sintering temperature of the fissile material, pressing the mixed fissile and additive materials into a pellet, sintering the pellet to a temperature greater than the melting point of the additive. Alternatively, if the melting point of the oxidation resistant particles is greater than the sintering temperature of UN or U3Si2, then the oxidation resistant particles can have a particle size distribution less than that of the UN or U3Si2.

Abstract: Disclosed herein is a method comprising coating a fissile, uranium-containing ceramic material with a water-resistant layer, the layer being non-reactive with the fissile, uranium-containing ceramic material. The coating is applied to a surface of the fissile, uranium-containing ceramic material. Also disclosed is a fuel for use in a nuclear reactor.

Abstract: The present disclosure provides a flexible display panel, a method for packaging the same, and a display device. The flexible display panel includes: a flexible substrate; a display element arranged on the flexible substrate; and a packaging layer covering the display element, the packaging layer including an inorganic thin film and an organic thin film that are stacked alternately, in which two protrusion structures that are engaged with each other are arranged between at least two adjacent thin films of the packaging layer.

Abstract: A method of forming a water resistant boundary on a fissile material for use in a water cooled nuclear reactor is described. The method comprises coating the fissile material, such as a pellet of U3Si2 and/or the grain boundaries, to a desired thickness with a suitable coating material, such as atomic layer deposition or a thermal spray process. The coating material may be any non-reactive material with a solubility at least as low as that of UO2. Exemplary coating materials include ZrSiO4, FeCrAl, Cr, Zr, Al—Cr, CrAl, ZrO2, CeO2, TiO2, SiO2, UO2, ZrB2, Na2O—B2O3—SiO2—Al2O3 glass, Al2O3, Cr2O3, carbon, and SiC, and combinations thereof. The water resistant layer may be overlayed with a burnable absorber layer, such as ZrB2 or B2O3—SiO2 glass.

Abstract: The present invention relates to nuclear fuel compositions including uranium dioxide with integral fuel burnable absorber, and triuranium disilicide and a composite of uranium mononitride and triuranium disilicide with or without integral fuel burnable absorber, and methods of sintering these compositions. The sintering is conducted using SPS/FAST apparatus and techniques. The sintering time and temperature is reduced using SPS/FAST as compared to conventional sintering methods for nuclear fuel compositions. The nuclear fuel compositions of the present invention are particularly useful in light water reactors.

Abstract: An improved nuclear fuel that has enhanced oxidation resistance and a process for making it are disclosed. The fuel comprises a composite of U235 enriched U3Si2 particles and an amount less than 30% by weight of UO2 particles positioned along the surface of the U3Si2 particles. The composite may be compressed into a pellet form. The process comprises forming a layer of UO2 on the surface of U3Si2 particles, either by exposing U3Si2 particles to an atmosphere of up to 15% oxygen by volume dispersed in an inert gas for a period of time and at a temperature sufficient to form UO2 at the U3Si2 particle surface, or by mixing U3Si2 particles with an amount up to 30% by weight of UO2 particles.

Abstract: A method of forming a water resistant boundary on a fissile material for use in a water cooled nuclear reactor is described. The method comprises mixing a powdered fissile material selected from the group consisting of UN and U3Si2 with an additive selected from oxidation resistant materials having a melting or softening point lower than the sintering temperature of the fissile material, pressing the mixed fissile and additive materials into a pellet, sintering the pellet to a temperature greater than the melting point of the additive. Alternatively, if the melting point of the oxidation resistant particles is greater than the sintering temperature of UN or U3Si2, then the oxidation resistant particles can have a particle size distribution less than that of the UN or U3Si2.

Abstract: The invention relates to compositions and methods for coating a zirconium alloy cladding of a fuel element for a nuclear water reactor. The composition includes a master alloy including one or more alloying elements selected from chromium, silicon and aluminum, a chemical activator and an inert filler. The alloying element(s) is deposited or are co-deposited on the cladding using a pack cementation process. When the coated zirconium alloy cladding is exposed to and contacted with water in a nuclear reactor, a protective oxide layer can form on the coated surface of the cladding.

Abstract: An improved nuclear fuel that has enhanced oxidation resistance and a process for making it are disclosed. The fuel comprises a composite of U235 enriched U3Si2 particles and an amount less than 30% by weight of UO2 particles positioned along the surface of the U3Si2 particles. The composite may be compressed into a pellet form. The process comprises forming a layer of UO2 on the surface of U3Si2 particles, either by exposing U3Si2 particles to an atmosphere of up to 15% oxygen by volume dispersed in an inert gas for a period of time and at a temperature sufficient to form UO2 at the U3Si2 particle surface, or by mixing U3Si2 particles with an amount up to 30% by weight of UO2 particles.

Abstract: A method of forming a water resistant boundary on a fissile material for use in a water cooled nuclear reactor is described. The method comprises coating the fissile material, such as a pellet of U3Si2 and/or the grain boundaries, to a desired thickness with a suitable coating material, such as atomic layer deposition or a thermal spray process. The coating material may be any non-reactive material with a solubility at least as low as that of UO2. Exemplary coating materials include ZrSiO4, FeCrAl, Cr, Zr, Al—Cr, CrAl, ZrO2, CeO2, TiO2, SiO2, UO2, ZrB2, Na2O—B2O3—SiO2—Al2O3 glass, Al2O3, Cr2O3, carbon, and SiC, and combinations thereof. The water resistant layer may be overlayed with a burnable absorber layer, such as ZrB2 or B2O3—SiO2 glass.

Abstract: The invention relates to compositions and methods for coating a zirconium alloy cladding of a fuel element for a nuclear water reactor. The composition includes a master alloy including one or more alloying elements selected from chromium, silicon and aluminum, a chemical activator and an inert filler. The alloying element(s) is deposited or are co-deposited on the cladding using a pack cementation process. When the coated zirconium alloy cladding is exposed to and contacted with water in a nuclear reactor, a protective oxide layer can form on the coated surface of the cladding.