A method for making an improved nuclear fuel cladding tube includes reinforcing a Zr alloy tube by first winding or braiding ceramic yarn directly around the tube to form a ceramic covering, then physically bonding the ceramic covering to the tube by applying a first coating selected from the group consisting of Nb, Nb alloy, Nb oxide, Cr, Cr oxide, Cr alloy, or combinations thereof, by one of a thermal deposition process or a physical deposition process to provide structural support member for the Zr tube, and optionally applying a second coating and optionally applying a third coating by one of a thermal deposition process or a physical deposition process. If the tube softens at 800° C.-1000° C., the structural support tube will reinforce the Zr alloy tube against ballooning and bursting, thereby preventing the release of fission products to the reactor coolant.

A method for making an improved nuclear fuel cladding tube includes reinforcing a Zr alloy tube by first winding or braiding ceramic yarn directly around the tube to form a ceramic covering, then physically bonding the ceramic covering to the tube by applying a first coating selected from the group consisting of Nb, Nb alloy, Nb oxide, Cr, Cr oxide, Cr alloy, or combinations thereof, by one of a thermal deposition process or a physical deposition process to provide structural support member for the Zr tube, and optionally applying a second coating and optionally applying a third coating by one of a thermal deposition process or a physical deposition process. If the tube softens at 800° C.-1000° C., the structural support tube will reinforce the Zr alloy tube against ballooning and bursting, thereby preventing the release of fission products to the reactor coolant.

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.

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.

Embodiments of the disclosure relate to a ferritic alloy having excellent ability to withstand nuclear power plant accidents and a method of manufacturing a nuclear fuel cladding tube using the same. The alloy includes iron (Fe), aluminum (Al), chromium (Cr), and nickel (Ni). The nickel (Ni) may be included 0.5 to 10 wt % based on a total amount of the alloy. The chromium may be included 13 to 18 wt % based on the total amount of the alloy. The aluminum may be included 5 to 7 wt % based on the total amount of the alloy.

Annular nuclear fuel rods are disclosed. The annular nuclear fuel rods include an outer cladding tube made of ceramic composite or cermet composite, an inner cladding tube made of ceramic composite or cermet composite, a nuclear fuel region located between the outer cladding tube and inner cladding tube, and an open channel for liquid coolant to flow.

Annular nuclear fuel rods are disclosed. The annular nuclear fuel rods include an outer cladding tube made of ceramic composite or cermet composite, an inner cladding tube made of ceramic composite or cermet composite, a nuclear fuel region located between the outer cladding tube and inner cladding tube, and an open channel for liquid coolant to flow.

Process for manufacturing a nuclear component comprising i) a support containing a substrate based on a metal (1), the substrate (1) being coated or not coated with an interposed layer (3) positioned between the substrate (1) and at least one protective layer (2) and ii) the protective layer (2) composed of a protective material comprising chromium; the process comprising a step a) of vaporizing a mother solution followed by a step b) of depositing the protective layer (2) onto the support via a process of chemical vapor deposition of an organometallic compound by direct liquid injection (DLI-MOCVD).

Process for manufacturing a nuclear component comprising i) a support containing a substrate based on a metal (1), the substrate (1) being coated or not coated with an interposed layer (3) positioned between the substrate (1) and at least one protective layer (2) and ii) the protective layer (2) composed of a protective material comprising chromium; the process comprising a step a) of vaporizing a mother solution followed by a step b) of depositing the protective layer (2) onto the support via a process of chemical vapor deposition of an organometallic compound by direct liquid injection (DLI-MOCVD).

The present disclosure relates to a high-strength Fe—Cr—Al—Ni multiplex stainless steel and a manufacturing method therefor. The multiplex stainless steel comprises 35 to 67 wt % of iron (Fe), 13 to 30 wt % of chrome (Cr), 15 to 30 wt % of nickel (Ni), and 5 to 15 wt % of aluminum (Al) and has a multiplex structure in which an austenite phase accounting for high ductility, a ferrite phase accounting for high strength, and an NiAl(B2) phase providing both strength and high-temperature steam oxidation resistance, exist in combination. The multiplex stainless steel can secure necessary fabricability and mechanical strength even if for/in a thin state, can maintain integrity as a structural member in a normal operation condition of a light-water reactor thanks to the formation of a chrome oxide layer thereon, and can form a stable oxide layer including alumina under a high-temperature steam environment, which is plausible in a high-temperature nuclear accident, thereby providing exceptionally improved resistance to serious accidents.