Abstract: A spacer of a fuel assembly having intersecting webs undergoes reduced longitudinal expansion as a result of corrosion during an operating period. The webs have intersection locations at which assembly gaps are provided. The assembly gaps have widths which correspond essentially, at most over a fraction of their total length, to the wall thickness of an intersecting web, but are wider in a remaining region. Since corrosion layers growing from an edge of an assembly gap toward the intersecting web cannot touch the web, no solid pressure, which could lead to longitudinal expansion, builds up.

Abstract: A spacer for a fuel assembly of a pressurized water reactor includes a first group of first webs standing on end and extending parallel to one another in a plane. Each of the first webs has longer sides and shorter sides. One of the longer sides of each of the first webs has a slit formed therein with a narrowed point and an impressed indentation. A second group of second webs stand on end and extend at right angles to the first webs. Each of the second webs has longer sides and shorter sides. Another of the longer sides of each of the second webs has a slit formed therein with a narrowed point and an impressed indentation. Each respective one of the first webs is connected to a respective one of the second webs to form a grid by inserting the webs into each other at the slits and locking the narrowed point of one web into place in the impressed indentation of another web with a plug-in connection.

Abstract: A nuclear power plant has a water or liquid sodium coolant and a metallic component having surfaces coming into contact with the coolant. A coating is disposed on the surfaces of the metallic component, such as fuel rod cladding tubes or spacer grids. The coating is formed of titanium carbide (TiC), titanium nitride (TiN), zirconium nitride (ZrN), chromium carbide (CrC), titanium aluminum vanadium nitride (TiAlVN), tantalum nitride (TaN), zirconium carbide (ZrC), or tungsten carbide (WC).

Abstract: In a nuclear reactor fuel element for receiving mutually parallel rods, the improvement includes a rectangular grid-shaped spacer including planar webs crossing and facing the rods defining grid mesh openings receiving the rods, the webs including two outer webs forming an outer corner of the spacer and defining a corner grid mesh opening at the outer corner, the outer corner having an outward curve being curved in a direction parallel to the longitudinal direction of the rods, the outer webs having edges at the curve transverse to the rods being drawn inward toward the rods in the corner grid mesh opening forming a bevel in longitudinal direction of the rod.

Abstract: Device for measuring the spring-force of resilient spacer projections set into spacer grids of nuclear reactor fuel assemblies to push fuel rods surrounded by spacer meshes against at least two oppositely disposed rigid spacer projections, including a force measuring plug having a diameter equal to the diameter of a fuel rod to be fixed in the spacer grid, and a flexible beam integral with the force measuring plug, the flexible beam having a free end in contact with a first resilient spacer projection to be measured, and another end firmly connected to the force measuring plug and having at least one wire strain gage disposed thereon.

Abstract: A nuclear reactor fuel rod formed of a cladding tube, end caps hermetically sealing the tube at both ends thereof, the tube being divided transversely into two longitudinal zones one of which is for receiving a charge of nuclear fuel and the other of which is for receiving gas-adsorbing material free of nuclear fuel, includes means received in the second zone for simultaneously supporting the tube and for containing gas-adsorbing material therein, the means having a capsule having an open end facing toward the one zone and a gas-permeable member closing off the open end of the capsule, the capsule containing adsorber material that has been dried and degassed in high vacuum at temperatures of from 500.degree. to 1000.degree. C, the capsule having an interior space between the adsorber material contained therein and the gas-permeable element, and including a metallic foil destructible by a given internal pressure of the fuel rod gas-tightly closing the interior space; and method of production.

Abstract: The invention relates to an apparatus for the assembly or permanent adhesion of sheets of glass with sheets of plastic material, comprising a pair of pressure rollers between which one passes the layers superimposed for assembly, which rollers being provided with, on a length corresponding at least with the size of the layers to be assembled, a hollow elastic covering which is filled with a fluid under pressure. In each roller the elastic covering is mounted to the roller (in a manner similar to a vehicle tire) by means of two rim-like elements, one of which is movable axially of the roller toward and from the other such rim. The elastic covering is like a tire but oversize in the axial direction. By adjusting one of the rims relative to the other, or the fluid pressure or both, the shape of the elastic tire-like member may be modified within wide limits to accommodate sheets of glass having complex, compound curves.

Abstract: For use in forming the core of a pressurized-water reactor, a fuel assembly supporting structure for holding a bundle of interspaced fuel rods, is formed by interspaced end pieces having holes in which the end portions of control rod guide tubes are inserted, fuel rod spacer grids being positioned by these guide tubes between the end pieces. The end pieces are fastened to the end portions of the guide tubes, to integrate the supporting structure, and in the case of at least one of the end pieces, this is done by means which releases that end piece from the guide tubes when the end pieces receive an abnormal thrust force directed towards each other and which would otherwise place the guide tubes under a compressive stress that would cause them to buckle. The spacer grids normally hold the fuel rods interspaced by distances determined by nuclear physics, and buckling of the control rod guide tubes can distort the fuel rod spacer grids with consequent dearrangement of the fuel rod interspacing.

Abstract: A moisture sensor is provided for a nuclear fuel rod for water-cooled nuclear reactors wherein moisture can be present. The fuel rod has an end cap and a charge of nuclear fuel. The moisture sensor is disposed between the end cap and the charge and serves to detect a leak in the fuel rod. The moisture sensor includes a capsule-like housing having an inner space and having openings through which moisture can pass into the inner space in the event of a leak in the fuel rod. Ferromagnetic material is disposed in the inner space of the housing together with a moisture detector responsive to moisture for altering the disposition of the ferromagnetic material in the inner space.