摘要:
Debris filters fit in fuel assembly lower tie plates and filter fluids passing therethrough. Filters use a series of adjacent plates with aligned peaks and valleys to create several channels. The plates have small excisions in diamond, triangle, or other debris-catching shapes, such as near a lower portion of the filter where fluid enters the filter. Excisions may alternate around each channel, such as four alternating cut-outs in 90-degree intervals about a channel circumference. Excisions may be sized to entrap smaller debris common in reactor coolant flow and liable for fretting damage to fuel cladding. Multiple vertical stages can be used in filters, with different channels for each stage. Ligaments may hold each stage to the next, potentially with a gap between stages for intermixing. Plates, peaks, valleys, ligaments, and excisions may all be formed in a single stamping operation to eliminate excess or overlapping pieces or extensions.
摘要:
Fuel spacers include at least one specialized bathtub on an outer perimeter band. Specialized bathtubs include an elastic resistive extension and a corresponding deflection limiter on a same outer face of the perimeter band. The elastic resistive extension provides flexible resistance to the channel, and the deflection limiter provides rigid movement limitation beyond a particular threshold between channel and spacer. The positioning, spring constant, length, number, and other properties of the specialized bathtub can be chosen based on the desired fuel assembly properties and expected transverse loads in fuel shipping and operation against which specialized bathtubs resiliently protect. The specialized bathtubs can be formed from a simplified stamp operation out of the perimeter band. Bathtubs can be placed on any position(s) on the perimeter band of example embodiment spacers used in nuclear fuel assemblies.
摘要:
Fuel assemblies include an outer channel having a physical configuration optimized for a position of the fuel assembly within a core of a nuclear reactor. The position of the fuel assembly with respect to an employed control blade in the nuclear reactor determines if the outer channel may be thickened, reinforced, and/or fabricated of Zircaloy-4 or similar distortion-resistant material, so as to reduce or prevent distortion of the channel against the control blade, or thinned so as to increase water volume and enhance reactivity in the assembly. Reactor cores having configured fuel assemblies include fuel assemblies having different outer channels. Methods include determining operational characteristics of the fuel assembly, including likelihood of being placed directly adjacent to an employed control blade, and physically selecting or modifying the outer channel of the fuel assembly based thereon.
摘要:
A system for removing particulates of a fissile material includes first and second filtration paths. A first filter and a first valve are disposed in the first filtration path. A second filter and a second valve are disposed in the second filtration path. The first valve and the second valve are configured to switch between a dual open state and a mixed open/closed state. During the dual open state, the first valve and the second valve axe open to permit concurrent flows of the effluent gas through the first and second filtration paths. During the mixed open/closed state, one of the first valve and the second valve is open while the other of the first valve and the second valve is closed to permit the particulates on a corresponding one of the first filter and the second filter to be dislodged by a countercurrent flow of a purging gas.
摘要:
Disclosed herein are zirconium-based alloys and methods of fabricating nuclear reactor components, particularly fuel cladding tubes, from such alloys that exhibit improved corrosion resistance in aggressive coolant compositions. The fabrication steps include a late-stage β-treatment on the outer region of the tubes. The zirconium-based alloys will include between about 1.30 and 1.60 wt % tin; between about 0.06 and 0.15 wt % chromium; between about 0.16 and 0.24 wt % iron, and between 0.05 and 0.08 wt % nickel, with the total content of the iron, chromium and nickel comprising above about 0.31 wt % of the alloy and will be characterized by second phase precipitates having an average size typically less than about 40 nm. The final finished cladding will have a surface roughness of less than about 0.50 μm Ra and preferably less then about 0.10 μm Ra.
摘要:
Disclosed are a fuel rod and a fuel bundle using the fuel rod. The fuel rod may include first enriched uranium in a boost zone of the fuel rod, wherein the boost zone may be arranged directly at a bottom of the fuel rod. The fuel rod may also include second enriched uranium in a second zone of the fuel rod, wherein the second zone is arranged over the boost zone. The fuel rod may also include natural uranium in a third zone of the fuel rod, wherein the third zone is arranged over the second zone. In this fuel rod, a percent of enrichment of the enriched uranium in the boost zone is at least one percent.
摘要:
Example embodiments are directed to tiered tie plates and fuel bundles that use tiered tie plates. Example embodiment tie plates may include upper and lower tiered tie plates. Example embodiment tiered tie plates may have a plurality of bosses divided into groups, or tiers, having differing vertical (axial) displacement. Example embodiment fuel bundles may use tiered tie plates such that fuel rods in example bundles may originate and terminate at different vertical displacements, based upon the vertical displacement of the bosses receiving the fuel rods into the tiered tie plates. Optionally, shanks may be used to further vary fuel rod axial displacement and diameter.
摘要:
In one embodiment, the method includes determining the safety limit minimum critical power ratio using the operating limit minimum critical power ratio, a change-in-critical-power-ratio distribution bias and a change-in-critical-power-ratio distribution standard deviation.
摘要:
An apparatus generating a graphical image of a core of a boiling water reactor (BWR) using at least one data set of channel deformation data including: a computer system including a display device for presenting the graphical image and a processor generating the graphical image using the at least one data set; the graphical image of the core includes symbolic representations of control blades arranged in the core, indicia identify each control blade, and indicia regarding deformation of channels adjacent each control blade, and a viewer software tool executed by the processor which accesses the at least one data set and determines a location in the core of the control blades and channels, and correlates the deformation data with the channels for display on the graphical image.
摘要:
Control rod guide tubes for a nuclear reactor having a body with an axial length that defines a lower end portion and an upper end portion and a cavity within a substantial length of the body. Orifices are included at the upper and lower end portions of the body. A control rod chamber is located within the cavity and is configured for receiving a control rod. A plurality of ports is coupled to the cavity and is positioned at a substantial length from the upper end portion of the body. Also included are at least two flow channels within the cavity that extend a substantial portion of the axial length of the body. Each flow channel is fluidly coupled to one or more of the ports for receiving fluid flow from outside the body and an outlet proximate to the upper end portion of the body for providing the received fluid flow.