Abstract: An apparatus for measuring fuel assembly bow and twist comprising a fixturing apparatus, a reference device and an ultrasonic measuring device.

Abstract: An electric load center having an enclosure with a push-in screw holder fixture, a door latch comprising a one-piece molded member having a flexible tongue which urges the door latch toward the hinged door edge keeping a hook biasedly engaged with an underside edge of the trim, a neutral bar having an elongated body portion with a trapezoidal shaped cross-sectional area with outwardly sloping downward extending side walls having apertures for insertion of electrical wires, a neutral tie bar adapted to be electrically connected to the enclosure of the load center, a main lug insulator having trough-shaped longitudinally extending compartments and first and second support legs for positioning over the neutral tie bar, a basepan having a surface with integrally formed posts with an undercut extending around its periphery for securing a component of the load center to the surface by heat staking, the surface having two spaced apart integrally formed wall members extending upward from the surface forming a barrier

Abstract: A nuclear fuel assembly for a boiling water reactor, comprising an outer channel having a substantially square cross-sectional area, and fuel rods arranged with a predetermined pitch in an array of 10.times.12 where the centers of the fuel rods are located at the vertices of equilateral triangles.

Abstract: A method of repairing a nuclear fuel rod assembly having a damaged fuel rod and/or a damaged spacer cell.

Abstract: A remote controlled circuit breaker providing thermal and magnetic overload current protection as well as remote load management capability.

Abstract: A moisture detection system for in-process nuclear fuel powder components includes a container within which the powder is located, a purge gas supply for providing a purge gas within the container, the purge gas contacting the powder and absorbing moisture therefrom, an off-gas line for transporting at least a portion of the purge gas after the purge gas contacts the powder, and a moisture detector for determining the moisture in the purge gas. The moisture content of the purge gas provides an indication of the moisture content of the powder. A process for detecting moisture of an in-process nuclear fuel powder component includes the steps of supplying a purge gas, contacting the powder with the purge gas, transporting at least a part of the purge gas through an off-gas line, and measuring the moisture of the purge gas in the off-gas line, the moisture measurement providing a measure of moisture in the powder.

Abstract: A method for determining the density of nuclear fuel pellet using gas displacement and isothermal gas expansion.

Abstract: A removable electrical receptacle adapted to be operatively connected to a continuous outlet cable having an insulating housing comprised of a case and a cover and having contacts for three electrical plugs.

Abstract: A boiling water reactor fuel assembly with fuel rods having variable fuel rod pitches.

Abstract: An electrical connector adapted to be operatively connected to a wall outlet and to continuous outlet cables. The connector includes an insulated housing, neutral, ground and line contact means for making contact with the neutral, ground and line wires of the outlet cable, and a rotatable plug to be operatively connected to the wall outlet and for making contact to the neutral, ground, and line contact means.

Abstract: Triangular lattice for LWR square fuel assemblies.

Abstract: A nuclear fuel assembly for a pressurized water reactor having lower and upper tie plates, guide tubes, spacer grids, an instrumentation tube, and extended fuel rods which extend to the lower tie plate and which are spaced radially and supported along the guide tubes by the spacer grids, at least one of the extended fuel rods having at a lower end a fuel rod lower end cap secured by a first spring within an aperture in the lower tie plate and which exerts a lateral force against the lower end cap. The upper tie plate further includes a fuel rod support housing which extends down over the upper end of the at least one of the extended fuel rods and has a second spring positioned in a bore in the fuel rod support housing which exerts a lateral force on the upper end of the extended fuel rod positioned within the bore in the fuel rod support housing.

Abstract: A method for retrofitting an irradiated nuclear fuel assembly including removing a portion of the inlet nozzle and installing a debris filter.

Abstract: The present invention provides a fuel rod for a light water nuclear reactors that comprises a part-length fuel rod and an extension tube having at least one wall member defining an enclosed flow path therethrough, the extension tube being coupled to a portion of the part-length fuel rod so as to be disposed axially above the part-length fuel rod, and including at least one inlet opening, for allowing fluid that surrounds the rod and initially comprises a two phase mixture of steam and liquid, to enter the enclosed fluid path and at least one outlet opening located above the inlet opening, the extension tube includes means for separating at least some of the steam located in the fluid from the liquid located therein. The improved fuel rod allows steam to bypass the upper active portions of the fuel assembly.

Abstract: A boiling water reactor fuel assembly having a lowered fuel rod support plate and increased fuel rod length while restraining the fuel rods against lateral vibration.

Abstract: A reactor coolant debris filter for insertion within a nuclear fuel assembly support.

Abstract: A method for retrofitting an irradiated nuclear fuel assembly including removing a portion of the inlet nozzle and installing a debris filter.

Abstract: A new configuration of a pressurized water reactor nuclear fuel assembly having a disengaging upper tie plate corner portion (60) which will disengage if the fuel assembly is unintentionally lifted, thus precluding the lifting of the fuel assembly from the reactor core and thereby avoiding the potential risk of dropping the irradiated nuclear fuel assembly.

Abstract: A nuclear fuel assembly for a boiling water reactor having a spacer grid for positioning and retaining the fuel rods. The spacer grid comprising an upper grid structure and a lower grid structure. Each grid structure comprises a first set of grid strips and a second set of grid strips which intersect to form in each grid structure a lattice of rectangular and square shaped cells through which the fuel rods extend and which act against the fuel rods within the cells. The lattice in each of the upper grid structure and the lower grid structure being the same. The upper grid structure and the lower grid structure being oriented relative to one another so that each of the rectangular and square shaped cells in the upper grid structure is superimposed on a corresponding one of the rectangular and square shaped cells in the lower grid structure so as to act cooperatively against and provide support to a fuel rod on four sides of the fuel rod.