Abstract: A filtering apparatus for a fluid intake of a nuclear power generation facility comprise primary and secondary frames. The primary frame defines an enclosed volume having least one inlet opening, and at least one outlet opening in fluid communication with the fluid intake. A primary filter is supported on the primary frame and covers the inlet opening such that fluid passes into the enclosed volume through the primary filter. The secondary frame is located within the volume enclosed by the primary frame. A secondary filter is supported on the secondary frame and defines an enclosed flow passage in communication with the outlet opening, such that fluid passes into the at least one outlet opening through the secondary filter and the enclosed flow passage.

Abstract: A seal assembly for a pump comprises a gland housing mounted to the pump casing. A staging flow pathway is defined within the gland housing with multiple seal chambers. A seal stage is positioned in each seal chamber, each having a static sealing element and a rotating sealing element, the sealing elements engaging one another to form a fluid-tight seal. A rotor assembly pumps coolant through the gland housing. Fluid passing through the staging flow pathway is accelerated by an acceleration surface of the rotor assembly. An inlet passage feeds coolant fluid into the staging flow pathway and past the acceleration surface.

Abstract: Apparatuses and methods for repairing a defect in a nuclear reactor are provided. The apparatus includes a body for insertion in a tubular structure, the body includes: an end effector having a weld torch operable to deposit weld material by forming molten weld droplets and depositing the weld droplets the tubular structure. A drive unit includes a brace for selectively anchoring against said tubular structure; at least one linear actuator for moving the apparatus relative to the brace; and a rotational actuator coupled to rotate the weld torch. The method includes inserting a repair apparatus into tubular structure of the nuclear reactor; moving the repair apparatus to a defect location; depositing a protective weld layer over the defect by sequentially depositing weld droplets atop a weld pool on the tubular structure, wherein the protective weld layer bonds to the tubular structure surrounding the defect.

Abstract: Methods and systems for detecting an individual leaking fuel channel included in a reactor. One system includes a plurality of inlet lines and a plurality of outlet lines. Each of the plurality of inlet lines feeding annulus fluid in parallel to an annulus space of each of a first plurality of fuel channels included in the reactor, and each of the plurality of outlet lines collecting in parallel annulus fluid exiting an annulus space of each of a second plurality of fuel channels included in the reactor. In some embodiments, the system also includes a detector positioned at an outlet of each of the plurality of outlet lines configured to detect moisture in annulus fluid and identify a first position of an individual leaking fuel channel, and an isolation valve positioned at an inlet of each of the plurality of inlet lines operable to stop annulus fluid from circulating through one of the plurality of inlet lines and to identify a second position of the individual leaking fuel channel.