Abstract:
A fuel channel assembly for a nuclear reactor may include an inner conduit received within an outer conduit that has an outer upper end connectable to a coolant outlet and an outer lower end. The inner conduit may have an inner upper end connectable to a coolant source and an inner lower end axially spaced apart from the inner upper end and disposed within the outer conduit to enable coolant to circulate from the coolant source to the coolant outlet through both the inner and outer conduits. A fuel bundle chamber may be between an inner surface of the outer conduit and an outer surface of the inner conduit and may at least partially laterally surround the inner conduit. The fuel bundle chamber fluidly connecting the inner lower end and the outer upper end to enable the coolant to flow upward through the fuel bundle chamber.
Abstract:
The present application pertains to a method of detecting and locating leaks in pipes having a secondary containment vessel. More particularly, the present application pertains to a method of leak detection whereby a tracer gas is introduced into the secondary containment vessel and detected in the primary pipe to determine the location of a leak in a primary pipe.
Abstract:
The present invention relates to filters used to remove debris from water being sucked into a piping system. It has particular application for use in nuclear power plants, which, after a loss of coolant accident, must pump cooling water back into the reactor core from a collection sump. This water may contain various types of debris that must be removed before the water is sent back into the reactor cooling system. Filtering of the debris is realized with the component known as "strainers". There are restrictions on the space available for installing strainers. The vaned filtering element, for example a vaned fin, of the present invention is designed to reduce the space required for strainer installation by increasing strainer surface area per unit volume, while maximizing the quantity of debris that can be filtered from the water.
Abstract:
An apparatus for adhering a filament to a surface can include a body having a filament inlet port, at least a first filament outlet port spaced apart from the filament inlet port, and at least a first filament travel path extending between the filament inlet port and the first filament outlet port. A reservoir chamber can form a portion of the first filament travel path between the filament inlet port and the first filament outlet port and can contain a viscous adhesive material. Imparting relative axial movement between the body and a first filament can urge the first filament along the first filament travel path and through the reservoir chamber so that the first filament is coated with the viscous adhesive material when exiting via the first filament outlet port, for adhesion to the surface.
Abstract:
A nuclear fuel bundle may include a first end face and a second end face axially spaced apart from the first end face and a plurality of elongate nuclear fuel elements supported by at least one spacer. The plurality of fuel elements and spacer being sized to be removably received within the fuel channel assembly. A coolant tube passage may extend axially through the fuel bundle between a first aperture in the first end face and a second aperture in the second end face. The coolant tube passage sized to removably receive a coolant fluid downflow tube provided in the fuel channel assembly. The tube passage extending from the first end face to the second end face to enable the coolant fluid downflow tube to pass through the fuel bundle.
Abstract:
It is common to store decayed radioactive waste in waste packages, lowered into vertical concrete cylindrical storage containers called tile holes. These containers of these packages decay over time and may become fragile, making it difficult to remove them using conventional methods. A retrieval tool has been developed, comprising a cylinder that fits between the tile hole internal diameter and the outside diameter of the waste package inside the tile hole. Inflatable air wedges are equally spaced inside the cylinder. The air wedges are inflated to a low pressure (2.1 psig) to provide uniform grip to the outside of the packages, minimizing the risk of damage to the decayed containers. A back-up system uses horizontal safety bars at the bottom of the cylinder, which may be rotated to form a partial platform under the waste package, preventing the package from falling in the event of a failure.