Fuel assembly for a nuclear reactor comprising a housing of longitudinal axis (X) having a central section containing nuclear-fuel pins and an upper section, forming a portion of the head of the assembly, containing a upper neutron shielding device (NSD) including neutron absorbers and means for reversibly interlocking with the housing and a moveable weight forming the head of the NSD, which is mounted so as to be able to move translationally relative to the rest of the NSD over a given path, said interlocking means being configured so that the NSD and the housing can be interlocked and uninterlocked by moving the moveable weight along the longitudinal axis by means of a grapple for extraction of the NSD, the claws of this grapple engaging with the moveable weight and the rest of the NSD being in downward longitudinal abutment in the interior of the housing.

A method comprises inserting the fuel rod (4) through the spacer grids (14) aligned along an assembling axis (A) with passing the fuel rod (4) through a lubrication chamber (30) aligned with the spacer grids (14) such that the lubrication chamber (30) is passed through by the fuel rod (4) before the insertion of the fuel rod (4) through one of the spacer grids (14), and circulating a lubrication fluid containing a gas and a lubricant in gaseous phase and/or mist form in the lubrication chamber (30). The lubrication fluid is injected in the lubrication chamber (30) at a temperature strictly higher than ambient temperature, such that lubricant deposits or condensates in liquid phase with forming a lubricant film on an external surface of the fuel rod (4) that is being inserted through said one of the spacer grids (14).

A method of monitoring in real time pressure resistance welding of a cladding tube and an end plug. The method includes: a first step of detecting welding information including voltage, current, and welding force in a process of pressure resistance welding of a cladding tube and an end plug; a second step of comparing static factors obtained by calculating effective values for the welding information with predetermined reference values, respectively; a third step of calculating dynamic factors for the welding information including the gradient of instantaneous welding force, when the reference values are satisfied in the second step; and a fourth step of determining whether there is defect or not in welding quality by comparing the dynamic factors.

A methodology is disclosed for compaction of a ceramic matrix of certain nuclear fuels incorporating neutron poisons, whereby those poisons aid in reactor control while aiding in fuel fabrication. Neutronic poisons are rare-earth oxides that readily form eutectics suppressing fuel fabrication temperature, of particular importance to the fully ceramic microencapsulated fuel form and fuel forms with volatile species.

A method of making a nuclear fuel pellet for a nuclear power reactor. The method includes providing a nuclear fuel material in powder form, pressing the powder such that a so-called green pellet is obtained, providing a liquid that comprises an additive which is to be added to the green pellet, contacting the green pellet with the liquid such that the liquid, with the additive, penetrates into the pellet, and sintering the so treated green pellet, wherein the additive is such that larger grains in the nuclear fuel material are obtained with the additive.

A method of making a nuclear fuel pellet for a nuclear power reactor. The method includes providing a nuclear fuel material in powder form, pressing the powder such that a so-called green pellet is obtained, providing a liquid that comprises an additive which is to be added to the green pellet, contacting the green pellet with the liquid such that the liquid, with the additive, penetrates into the pellet, and sintering the so treated green pellet, wherein the additive is such that larger grains in the nuclear fuel material are obtained with the additive.

A nuclear reactor fuel assembly includes a plurality of fuel rods, a plurality of guide channels, two nozzles, one of which has a bearing plate with openings, elements for the detachable connection of the nozzles to the guide channels, a detachable connection locking device and locking device fasteners. The elements for the detachable connection of the nozzles to the guide channels have a cross-section size greater than the size of openings in the nozzle bearing plate.

A nuclear reactor fuel assembly includes a plurality of fuel rods, a plurality of guide channels, two nozzles, one of which has a bearing plate with openings, elements for the detachable connection of the nozzles to the guide channels, a detachable connection locking device and locking device fasteners. The elements for the detachable connection of the nozzles to the guide channels have a cross-section size greater than the size of openings in the nozzle bearing plate.

A modular water purification system for a nuclear power plant includes a plurality of modules that may be selectively connected together directly or through the use of intermediary adapters in a plurality of arrangements. The modules may include a pump module, a FOSAR module, a particulate filtration module, a cross-flow filtration module, a degasification module, and/or a demineralization module, among other possible modules. The modules may have common interfaces so that they can be interconnected (directly or through intermediary adapters) in a variety of configurations for different purposes within the context of the nuclear power plant (e.g., filtering pool water; collecting large objects via vacuuming). Various modules may have form factors and/or mounting structures that are similar enough to the fuel assemblies of the plant that (1) the plant's fuel assembly handling equipment can grab, move, and reposition the modules, and/or (2) the modules may be stored in the fuel pool's storage rack.

A modular water purification system for a nuclear power plant includes a plurality of modules that may be selectively connected together directly or through the use of intermediary adapters in a plurality of arrangements. The modules may include a pump module, a FOSAR module, a particulate filtration module, a cross-flow filtration module, a degasification module, and/or a demineralization module, among other possible modules. The modules may have common interfaces so that they can be interconnected (directly or through intermediary adapters) in a variety of configurations for different purposes within the context of the nuclear power plant (e.g., filtering pool water; collecting large objects via vacuuming). Various modules may have form factors and/or mounting structures that are similar enough to the fuel assemblies of the plant that (1) the plant's fuel assembly handling equipment can grab, move, and reposition the modules, and/or (2) the modules may be stored in the fuel pool's storage rack.