Westinghouse Electric Company LLC

Calgon Carbon Corporation

Kuraray Co., Ltd.

Jason P Mazzoccoli

Peng Xu

Edward Jean Lahoda

Walter George Tramposch

Ryan W Walker

William A Byers

Robert H Vaughn

Sumit Ray

Keita Takahashi

Richard J Jacko

Carroll J Long, Jr

Steven L Butterworth

Deborah J Buckley

Aya Benzaki

Grant L Eddy

Rachel L Devito

Edward J Silva

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.

Sorbents for immersion cooling

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.

Iron and nitrogen treated sorbent and method for making same

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.

Copper, iron, and nitrogen treated sorbent and method for making same

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.

Copper and nitrogen treated sorbent and method for making same

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.

Deposition of integrated protective material into zirconium cladding for nuclear reactors by high-velocity thermal application

Sorbent materials are described that have enhanced performance in removing chlorine and chloramine, among other toxic compounds. The sorbent materials are formed by a process which includes steps of oxidation, adding a nitrogen-containing compound, and calcining the sorbent. The processes of forming the sorbent materials are also disclosed. The sorbent materials have excellent performance as measured by a chloramine and/or chlorine destruction number, and the sorbents retain a high nitrogen edge concentration. The sorbent materials may also be incorporated into devices such as filter assemblies.

Chloramine and chlorine removal material and methods for making the same

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.

Chemical process for primary system material passivation during hot functional testing of nuclear power plants

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.

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 ZrAlC ceramic, TiAlC ceramic, TiAlCceramic, AlO, aluminum, zirconium silicide, amorphous and semi-amorphous alloyed stainless steel, and mixtures of ZrAlC ceramic, TiAlC ceramic and TiAlCceramic. 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.

Kinetically applied gradated Zr-Al-C ceramic or Ti-Al-C ceramic or amorphous or semi-amorphous stainless steel with nuclear grade zirconium alloy metal structure

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.

Deposition of a protective coating including metal-containing and chromium-containing layers on zirconium alloy for nuclear power applications

A zirconium alloy nuclear reactor cylindrical cladding has an inner Zr substrate surface (), an outer volume of protective material () consisting of Zr&#x2014;Al, 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.

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Pittsburgh, PA, United States of America

Jason P Mazzoccoli