A composite nuclear reactor component comprises a support and a protective layer (2). The support contains a substrate (1) based on a metal. The substrate is coated with an interposed layer (3) positioned between the substrate (1) and the protective layer (2). The protective layer (2) is composed of a material which comprises amorphous chromium carbide. The nuclear reactor component provides for improved resistance to oxidation, hydriding, and/or migration of undesired material.

The end plug includes two parts in the form of coaxial cylinders having different diameters, the diameter of the part configured to be arranged inside the cladding is less than the cladding inner diameter by 0.06-0.08 and 2-3 mm, respectively, for interposing brazes of different types. An end plug according to the third variant is composed of three parts in the form of three successively arranged coaxial cylinders having different diameters, the diameter of the two parts configured to be arranged inside the cladding being less than the cladding inner diameter by 0.06-0.08 and 2-3 mm, respectively, for interposing brazes of two types simultaneously. The effects of the invention are safety for the environment, possibility of using the developed end plugs as an alternative for replacing plugs used in various reactors, proposal of a simplified method for manufacturing an end plug, improvements in mechanical and thermophysical properties of end plugs.

The present disclosure is generally related to methods, systems and devices for forming a randomized grain structure coating on a substrate of a component for use in a nuclear reactor to provide protection against corrosion and, more particularly, is directed to improved methods, systems and devices for forming a randomized grain structure coating on a zirconium alloy nuclear fuel cladding tube using a cathodic arc (CA) physical vapor deposition (PVD) process to provide protection against corrosion in both normal operation and in transient and accidents of the nuclear reactor.

The present disclosure is generally related to methods, systems and devices for forming a randomized grain structure coating on a substrate of a component for use in a nuclear reactor to provide protection against corrosion and, more particularly, is directed to improved methods, systems and devices for forming a randomized grain structure coating on a zirconium alloy nuclear fuel cladding tube using a cathodic arc (CA) physical vapor deposition (PVD) process to provide protection against corrosion in both normal operation and in transient and accidents of the nuclear reactor.

A nuclear fuel cladding tube is described herein that includes a zirconium alloy tube having an outer wear and oxidation resistant ceramic coating selected from the group consisting of CrN, Cr.sub.2N, CrWN, CrZrN, and combinations thereof. The cladding may have an intermediate layer formed between the tube and the outer ceramic coating. The intermediate layer may be selected from the group consisting of Ta, W, Mo, Nb, and combinations thereof. Both the intermediate layer and the outer ceramic coating may be deposited by physical vapor deposition.

A nuclear fuel cladding tube is described herein that includes a zirconium alloy tube having an outer wear and oxidation resistant ceramic coating selected from the group consisting of CrN, Cr.sub.2N, CrWN, CrZrN, and combinations thereof. The cladding may have an intermediate layer formed between the tube and the outer ceramic coating. The intermediate layer may be selected from the group consisting of Ta, W, Mo, Nb, and combinations thereof. Both the intermediate layer and the outer ceramic coating may be deposited by physical vapor deposition.

Composite structures are provided whose composite matrix is a fully-dense (greater than 95%) magnesium oxide-containing phase and whose entrained phase, by virtue of its' decomposition temperature or chemical reactivity, would otherwise not be fabricable. Notably, a methodology is provided whereby a range of composite structures are formed by applying an advanced manufacturing technique and a blend of ceramic powder whose sintering is enhanced by small amounts of a metal halide sintering aid. This methodology and process significantly lowers the processing temperature of refractory ceramics such as magnesium oxide allowing formation of ceramic bodies incorporating phases such as metal hydrides, fragile ceramic phases, and highly reactive species such as beryllides. In all cases, the final product is substantially-free, or even devoid, of the metal halide sintering aid, resulting in a phase-pure ceramic matrix composed of the host phase and the entrained phase.

The method includes forming an inner monolithic layer from crystals of beta phase stoichiometric silicon carbide on a carbon substrate in the form of a rod by chemical methylsilane vapor deposition in a sealed tubular hot-wall CVD reactor. The method further includes forming a central composite layer over the inner monolithic layer by twisting continuous beta phase stoichiometric silicon carbide fibers into tows, transporting the tows to a braiding machine, and forming a reinforcing thread framework. A pyrocarbon interface coating is built up by chemical methane vapor deposition in a sealed tubular hot-wall CVD reactor. Then, a matrix is formed by chemical methylsilane vapor deposition in the reactor. A protective outer monolithic layer is formed from crystals of beta phase stoichiometric silicon carbide over the central composite layer by chemical methylsilane vapor deposition in a CVD reactor. And then the carbon substrate is removed from the fabricated semi-finished product.

The method includes forming an inner monolithic layer from crystals of beta phase stoichiometric silicon carbide on a carbon substrate in the form of a rod by chemical methylsilane vapor deposition in a sealed tubular hot-wall CVD reactor. The method further includes forming a central composite layer over the inner monolithic layer by twisting continuous beta phase stoichiometric silicon carbide fibers into tows, transporting the tows to a braiding machine, and forming a reinforcing thread framework. A pyrocarbon interface coating is built up by chemical methane vapor deposition in a sealed tubular hot-wall CVD reactor. Then, a matrix is formed by chemical methylsilane vapor deposition in the reactor. A protective outer monolithic layer is formed from crystals of beta phase stoichiometric silicon carbide over the central composite layer by chemical methylsilane vapor deposition in a CVD reactor. And then the carbon substrate is removed from the fabricated semi-finished product.

A nuclear fuel cladding with improved thermomechanical properties is provided. The nuclear fuel cladding includes a double-walled construction having inner and outer hexagonal sidewalls. The inner sidewall and the outer sidewall are spaced apart from each other to form a cooling channel therebetween, and the inner sidewall surrounds a nuclear fuel and is spaced apart from the nuclear fuel by a small gap. Helical fins extend into the cooling channel to interconnect the inner sidewall and the outer sidewall. Resilient fingers extend toward the nuclear fuel through the small gap to comply with variations in the size of the nuclear fuel due to fabrication tolerances as well as thermal expansion and swelling of the nuclear fuel, for example UO.sub.2, when undergoing fission. The nuclear fuel cladding is formed according to an additive manufacturing process, for example laser powder bed fusion printing.