Abstract: By using a boric acid-resistant anion exchange resin as the anion exchange resin used in a demineralizer that purifies the primary cooling water in a pressurized-water reactor power plant, even when a boric acid-containing primary cooling water is brought into contact with the anion exchange resin disposed in the demineralizer, the generation of breaking or cracking in the anion exchange resin can be prevented.

Abstract: A device is provided to inspect welds in nozzles located in water within a containment vessel of a nuclear power plant. A computer connected to the device controls movement by use of thrusters located along a main rail while buoyancy packs regulate the depth. After the device is navigated to a weld needing inspection, feet extend radially outward from the main rail to secure the device in the nozzle. Then transducer clusters are moved along the main rail to be radially inside the weld to be inspected. Thereafter, the transducer clusters are extended radially outward and rotated adjacent to the weld while simultaneously emitting test signals and receiving reflected signals to indicate the condition of the weld.

Abstract: An apparatus and method for maintaining contact between a pod of transducers and an inner surface of a reactor pressure vessel filled with water of a nuclear power plant is described. An underwater carriage carries the pod of transducers each of which is independently movable and are constantly urged against the surface of the vessel during inspection. Each transducer is independently pivotable about two axes. Each transducer emits and receives signals to detect any flaws of potential problems in the reactor pressure vessel.

Abstract: A method for extracting tritium from irradiated boiling water reactor control rods that have cruciform-shaped. Bands of a malleable metal are wrapped around the flat portions of the blades, one band near the top of each blade panel and a second band near the bottom. The bands are crimped and an inlet penetration is formed through one of the bands and the panel and an outlet penetration is formed through the second band and the panel. A termination of each end of a closed loop conduit is sealably connected to the inlet and outlet for transporting a carrier gas through the interior of the panel. The carrier gas passing through the interior transports the tritium out of the panel to a tritium getter filter to capture the tritium. The carrier gas then recirculates through the system.

Abstract: A CRDS unlatching tool includes a support assembly and a latching assembly, wherein the support assembly is received within the latching assembly in a manner wherein the latching assembly is moveable relative to the support assembly. The support assembly has a plurality of latch fingers and at least one pin, each of the latch fingers being movable between a latched position wherein the latch finger is structured to engage and hold the CRDS an unlatched position wherein the latch finger is structured to not engage the CRDS. The latching assembly includes a first sleeve member and a second sleeve member, the second sleeve member having at least one slot, wherein the at least one pin is moveably received within the at least one slot. The latching assembly is movable from a latched state to an unlatched state wherein the latch fingers are actuated by the first sleeve member.

Abstract: A nuclear reactor module includes a reactor vessel containing coolant, a reactor core submerged in the coolant, and a heat exchanger configured to remove heat from the coolant. The nuclear reactor module further includes one or more heaters configured to add heat to the coolant during a startup operation and prior to the reactor core going critical.