Abstract: Carbonaceous material that is activated to form precursor activated carbon is further enhanced by doping with copper and nitrogen and calcining. The resultant sorbent material has excellent catalytic properties which are useful in the field of fluid purification.

Abstract: Carbonaceous material that is activated to form precursor activated carbon is further enhanced by doping with copper and nitrogen and calcining. The resultant sorbent material has excellent catalytic properties which are useful in the field of fluid purification.

Abstract: The present application relates to activated carbon compositions for removing viral, bacterial, or other infectious particles from air. The activated carbon was found to be effective at filtering aerosolized bacteriophage particulates and could be applied to barrier materials which prevents viral particulates from passing through, for example in home filters or masks or other coverings to prevent the spread of infectious diseases.

Abstract: Sorbent for filtering a coolant in immersion cooling systems, such as those used to cool electronic components. Sorbent may comprise activated carbon sorbent materials that have a bulk oxygen content of about 1 wt. % to about 5 wt. %, a moisture level of at most about 1.5 wt. %, and a molasses number of at least about 150. Sorbents may be contained within an enclosure to convey coolant therethrough to remove conductive contaminants from the coolant.

Abstract: Carbonaceous material that is activated to form precursor activated carbon is further enhanced by doping with copper, iron, and nitrogen and calcining. The carbonaceous material includes those obtained from coal, wood, or coconut shells. Methods of doping the activated carbon are described. The described treatment processes result in a sorbent material that has excellent performance in removing chloramine and similar compounds from fluids such as water that is intended for drinking.

Abstract: Carbonaceous material that is activated to form precursor activated carbon is further enhanced by doping with iron and nitrogen and calcining. The resultant sorbent material has excellent catalytic properties which are useful in the field of fluid purification. The further enhancement can be performed in a single stage process or a dual stage process. The carbonaceous material includes those obtained from coal, wood, or coconut shells. The described treatment processes result in a sorbent material that has excellent performance in removing chloramine and similar compounds from fluids such as water that is intended for drinking.

Abstract: Carbonaceous material that is activated to form precursor activated carbon is further enhanced by doping with copper and nitrogen and calcining. The resultant sorbent material has excellent catalytic properties which are useful in the field of fluid purification.

Abstract: A zirconium alloy nuclear reactor cylindrical cladding has an inner Zr substrate surface, an outer volume of protective material, and an integrated middle volume of zirconium oxide, zirconium and protective material, where the protective material is applied by impaction at a velocity greater than 340 meters/second to provide the integrated middle volume resulting in structural integrity for the cladding.

Abstract: The present invention relates to a pre-core hot functional testing (HFT) preconditioning process, which includes the introduction of chemical additives, e.g., zinc, into coolant water that circulates through the primary system of a new nuclear power plant, at various temperatures. The chemical additives contact the primary system surfaces, which results in the formation of a protective zinc-containing oxide film on the fresh surfaces to control corrosion release and deposition during subsequent normal operation of the nuclear power plant. The method includes a series of three chemistry phases to optimize the passivation process: 1) an alkaline-reducing phase, 2) an acid-reducing phase and 3) an acid-oxidizing phase.

Abstract: A zirconium alloy nuclear reactor cylindrical cladding has an inner Zr substrate surface, an outer volume of protective material, and an integrated middle volume of zirconium oxide, zirconium and protective material, where the protective material is applied by impaction at a velocity greater than 340 meters/second to provide the integrated middle volume resulting in structural integrity for the cladding.

Abstract: A zirconium alloy nuclear reactor cylindrical cladding has an inner Zr substrate surface (10), an outer volume of protective material (22), and an integrated middle volume (20) of zirconium oxide, zirconium and protective material, where the protective material is applied by impaction at a velocity greater than 340 meters/second to provide the integrated middle volume (20) resulting in structural integrity for the cladding.

Abstract: A composition and method of kinetically depositing the composition to form a coating onto an exterior surface of a zirconium alloy cladding of a light water nuclear reactor which at least partially adheres to the exterior surface. The coating composition includes a first component and a second component. The first component is selected from the group consisting of zirconium, zirconium oxide and mixtures thereof. The second component is selected from the group consisting of Zr2AlC ceramic, Ti2AlC ceramic, Ti3AlC2 ceramic, Al2O3, aluminum, zirconium silicide, amorphous and semi-amorphous alloyed stainless steel, and mixtures of Zr2AlC ceramic, Ti2AlC ceramic and Ti3AlC2 ceramic. The coating has a gradient emanating from the exterior surface of the cladding toward an exposed outer surface of the coating such that percent by weight of the first component decreases and the second component increases from the exterior surface of the cladding toward the exposed outer surface of the coating.

Abstract: A composition and method of kinetically depositing the composition to form a coating onto an exterior surface of a zirconium alloy cladding of a light water nuclear reactor which at least partially adheres to the exterior surface. The coating composition includes a first component and a second component. The first component is selected from the group consisting of zirconium, zirconium oxide and mixtures thereof. The second component is selected from the group consisting of Zr2AlC ceramic, Ti2AlC ceramic, Ti3AlC2 ceramic, Al2O3, aluminum, zirconium silicide, amorphous and semi-amorphous alloyed stainless steel, and mixtures of Zr2AlC ceramic, Ti2AlC ceramic and Ti3AlC2 ceramic. The coating has a gradient emanating from the exterior surface of the cladding toward an exposed outer surface of the coating such that percent by weight of the first component decreases and the second component increases from the exterior surface of the cladding toward the exposed outer surface of the coating.

Abstract: A composition and method of kinetically depositing the composition to form a coating onto an exterior surface of a zirconium alloy cladding of a light water nuclear reactor which at least partially adheres to the exterior surface. The coating composition includes a first component and a second component. The first component is selected from the group consisting of zirconium, zirconium oxide and mixtures thereof. The second component is selected from the group consisting of Zr2AlC ceramic, Ti2AlC ceramic, Ti3AlC2 ceramic, Al2O3, aluminum, zirconium silicide, amorphous and semi-amorphous alloyed stainless steel, and mixtures of Zr2AlC ceramic, Ti2AlC ceramic and Ti3AlC2 ceramic. The coating has a gradient emanating from the exterior surface of the cladding toward an exposed outer surface of the coating such that percent by weight of the first component decreases and the second component increases from the exterior surface of the cladding toward the exposed outer surface of the coating.

Abstract: The invention relates to compositions and methods for coating a zirconium alloy cladding of a fuel element for a nuclear water reactor. The coating includes a first tier or layer and a second tier or layer. The first layer includes an elemental metal and the second layer is an oxidation-resistant layer that includes elemental chromium. The first layer serves as an intermediate layer between the zirconium alloy substrate and the second layer. This intermediate layer can be effective to improve adhesion of the second layer to the zirconium alloy substrate. The multilayer coating forms a protective layer which provides improved capability for the zirconium alloy cladding to withstand normal and accident conditions to which it is exposed in the nuclear reactor.

Abstract: A zirconium alloy nuclear reactor cylindrical cladding has an inner Zr substrate surface (10), an outer volume of protective material (22), and an integrated middle volume (20) of zirconium oxide, zirconium and protective material, where the protective material is applied by impaction at a velocity greater than 340 meters/second to provide the integrated middle volume (20) resulting in structural integrity for the cladding.

Abstract: A zirconium alloy nuclear reactor cylindrical cladding has an inner Zr substrate surface (10), an outer volume of protective material (22) consisting of Zr—Al, and an integrated middle volume (20) of zirconium oxide, zirconium and protective material, where the protective material is applied by impaction at a velocity greater than 340 meters/second to provide the integrated middle volume (20) resulting in structural integrity for the cladding.

Abstract: The present invention relates to a pre-core hot functional testing (HFT) preconditioning process, which includes the introduction of chemical additives, e.g., zinc, into coolant water that circulates through the primary system of a new nuclear power plant, at various temperatures. The chemical additives contact the primary system surfaces, which results in the formation of a protective zinc-containing oxide film on the fresh surfaces to control corrosion release and deposition during subsequent normal operation of the nuclear power plant. The method includes a series of three chemistry phases to optimize the passivation process: 1) an alkaline-reducing phase, 2) an acid-reducing phase and 3) an acid-oxidizing phase.

Abstract: The invention relates to compositions and methods for coating a zirconium alloy cladding of a fuel element for a nuclear water reactor. The coating includes a first tier or layer and a second tier or layer. The first layer includes an elemental metal and the second layer is an oxidation-resistant layer that includes elemental chromium. The first layer serves as an intermediate layer between the zirconium alloy substrate and the second layer. This intermediate layer can be effective to improve adhesion of the second layer to the zirconium alloy substrate. The multilayer coating forms a protective layer which provides improved capability for the zirconium alloy cladding to withstand normal and accident conditions to which it is exposed in the nuclear reactor.

Abstract: A zirconium alloy nuclear reactor cylindrical cladding has an inner Zr substrate surface (10), an outer volume of protective material (22), and an integrated middle volume (20) of zirconium oxide, zirconium and protective material, where the protective material is applied by impaction at a velocity greater than 340 meters/second to provide the integrated middle volume (20) resulting in structural integrity for the cladding.