A fast-neutron nuclear reactor fuel assembly having fuel rods. Each fuel rod has nuclear fuel disposed in a sealed housing in the form of a tubular steel shell and end parts. A steel spacer element is wound in a coil with a specific pitch on the outside surface of the shell and is fastened on the end parts. The spacer element is in the form of a metallic band twisted around its longitudinal axis. The width of said band is approximately equal to the minimum distance between adjacent fuel rods in the fuel assembly. A transverse cross-sectional area of the band is within a range from 0.10 to 0.50 times the area of a circle described around the width of the band.

A fast-neutron nuclear reactor fuel assembly having fuel rods. Each fuel rod has nuclear fuel disposed in a sealed housing in the form of a tubular steel shell and end parts. A steel spacer element is wound in a coil with a specific pitch on the outside surface of the shell and is fastened on the end parts. The spacer element is in the form of a metallic band twisted around its longitudinal axis. The width of said band is approximately equal to the minimum distance between adjacent fuel rods in the fuel assembly. A transverse cross-sectional area of the band is within a range from 0.10 to 0.50 times the area of a circle described around the width of the band.

A nuclear reactor core mechanical support bracket is disclosed. The support bracket includes a housing, a spring disposed internally within the housing, a shaft slidingly disposed within the housing and to engage the spring to compress and decompress the spring as the shaft travels in and out of the housing, a shaft travel pin to control the travel of the shaft, and a flange to mount the support bracket to a canister of a nuclear reactor. The shaft includes an inset configured to interface with a nuclear reactor core component.

A nuclear reactor has a core installed on a lower core plate and formed from multiple fuel assemblies, each fuel assembly including a structural cage assembly. The structural cage assembly has an upper end fitting, mid grids, and a lower end fitting (LEF). The LEF positions the fuel assembly using four locating pins located at each corner of the LEF. The pins position the fuel assembly laterally by mating with receiving holes in the lower core plate. The locating pins have a chamfered tip with a flat end. The chamfered tip allows for a greater positioning margin when installing the fuel assembly in the core by guiding the pins into holes in the lower core plate, and the flat tip provides strength and stability in case the assembly is inadvertently rested on the tip of the pin instead of the LEF pads.

A nuclear reactor has a core installed on a lower core plate and formed from multiple fuel assemblies, each fuel assembly including a structural cage assembly. The structural cage assembly has an upper end fitting, mid grids, and a lower end fitting (LEF). The LEF positions the fuel assembly using four locating pins located at each corner of the LEF. The pins position the fuel assembly laterally by mating with receiving holes in the lower core plate. The locating pins have a chamfered tip with a flat end. The chamfered tip allows for a greater positioning margin when installing the fuel assembly in the core by guiding the pins into holes in the lower core plate, and the flat tip provides strength and stability in case the assembly is inadvertently rested on the tip of the pin instead of the LEF pads.

A debris filtering skirt configured for use with a flow plate of a bottom nozzle of a nuclear reactor is disclosed herein. The debris filtering skirt includes a base portion defining an opening between a bottom edge and a reactor vessel lower core plate, and the opening includes a dimension configured to position the bottom nozzle a predetermined distance away from the reactor vessel lower core plate. The debris filtering skirt also includes a plurality of holes, and at least one hole of the plurality of holes includes a dimension determined based, at least in part, on a predetermined size of debris capable of traversing through the inlet and the outlet. The dimension of the opening and the dimension of the at least one hole are determined based, at least in part, on a predetermined loss coefficient of the bottom nozzle.

A debris filtering skirt configured for use with a flow plate of a bottom nozzle of a nuclear reactor is disclosed herein. The debris filtering skirt includes a base portion defining an opening between a bottom edge and a reactor vessel lower core plate, and the opening includes a dimension configured to position the bottom nozzle a predetermined distance away from the reactor vessel lower core plate. The debris filtering skirt also includes a plurality of holes, and at least one hole of the plurality of holes includes a dimension determined based, at least in part, on a predetermined size of debris capable of traversing through the inlet and the outlet. The dimension of the opening and the dimension of the at least one hole are determined based, at least in part, on a predetermined loss coefficient of the bottom nozzle.

The present inventive concept provides a method for manufacturing a multi-layered nuclear fuel cladding pipe, comprising the steps of: providing a preliminary cladding pipe in which an inner pipe having a rod-shaped insertion body inserted thereinto is disposed in an outer pipe; reducing the diameter of the preliminary cladding pipe by applying pressure from the outside to the inner side of the preliminary cladding pipe; and removing the insertion body from the inner pipe by providing a force in the direction in which the insertion body extends, wherein the inner pipe and the outer pipe may be formed of different metals from each other.

The present inventive concept provides a method for manufacturing a multi-layered nuclear fuel cladding pipe, comprising the steps of: providing a preliminary cladding pipe in which an inner pipe having a rod-shaped insertion body inserted thereinto is disposed in an outer pipe; reducing the diameter of the preliminary cladding pipe by applying pressure from the outside to the inner side of the preliminary cladding pipe; and removing the insertion body from the inner pipe by providing a force in the direction in which the insertion body extends, wherein the inner pipe and the outer pipe may be formed of different metals from each other.

.sup.210Pb and .sup.227Ac are used in thermal energy production as precursor isotopes, which have been isolated and are allowed to age to the point of secular equilibrium with their progeny, referring to the decay product isotopes in the radioactive decay chain of each. Both .sup.210Pb and .sup.227Ac are in the radioactive decay chains of naturally occurring uranium isotopes, and are each subject to their own natural radioactive decay. While not particularly energetic through their own decay, they (1) are separable from their parent isotopes or may be created in a reactor, (2) have half-lives of around 22 years, and (3) are precursors (natural radioactive decay parents) to subsequent rapid and energetic decay processes. These two isotopes can offer significant advantages as RPS fuel compared to the currently used .sup.238Pu.