Abstract: A flange flush tool includes an outer tube having a first end and a second end, the first end configured to engage the flange, and a shield tube within the outer tube. A channel is defined between an outer surface of the shield tube and an inner surface of the outer tube. The shield tube is configured to move longitudinally within the outer tube.

Abstract: A method and apparatus for a deposition solution injector for a nuclear reactor that may inject an ambient temperature deposition solution into a high temperature, high pressure feed-water flow line. The method and the apparatus ensures that the deposition solution is delivered in a location within the feed-water that is beyond a boundary layer of flowing water, to prevent smearing of the solution and prevent clogging of the deposition solution within the injector. The axial cross-sectional profile of the injector, and the location of an injection slot on the injector, may reduce vortex eddy flow of the feed-water into the injector to further reduce injector blockage.

Abstract: A method of fabricating metallic fuel from surplus plutonium may include combining plutonium oxide powder and uranium oxide powder to obtain a mixed powder with reduced proliferation potential. The mixed powder may be electroreduced in a bath of molten salt so as to convert the mixed powder to a first alloy. The first alloy may be pressed to remove a majority of the molten salt adhered to the first alloy to form a pressed alloy-salt mixture. The first alloy may be isolated from the salt by melting the pressed alloy-salt mixture. The first alloy may be further processed to fabricate a fuel rod. Accordingly, the metallic fuel produced may be used in a fast reactor system, such as a Power Reactor Innovative Small Module (PRISM).

Abstract: A system and method for conducting Non-Destructive Examination (NDE) inspections and integrating inspection data with encoding information may include a NDE probe configured to conduct a non-destructive examination of an object, a shape sensing fiber optic cable attached to the NDE probe, the fiber optic cable configured to receive a frequency of light and to reflect the received light, a fiber optic cable shape sensing detector configured to generate light of the frequency, measure the shape of the shape sensing fiber optic cable based on the reflected light from the shape sensing fiber optic cable, and determine position information and orientation information of the NDE probe based on the measured shape of the fiber optic cable, and a processor configured to encode the examination data, the encoding including correlating the position information and the orientation information with the examination data.

Abstract: A system and a method for injecting hydrogen into Boiling Water Reactor (BWR) reactor support systems in operation during reactor startup and/or shutdown to mitigate Inter-Granular Stress Corrosion Cracking (IGSCC). The system may provide hydrogen at variable pressures (including relatively higher pressures) that match changing operating pressures of the reactor supports systems as the reactor cycles through startup and shutdown modes.

Abstract: A method of cleaning a jet pump assembly of a nuclear reactor may comprise evacuating an interior of the jet pump assembly that is filled with a first liquid by injecting a gas to purge the first liquid from the interior to provide an evacuated surface. In addition, the method may comprise directing a jet of a second liquid onto the evacuated surface.

Abstract: A method of making a nuclear fuel structure may include reducing a metal oxide in a cathode assembly so as to deposit a metal of the metal oxide on the cathode plate of the cathode assembly, and processing the cathode plate with the metal deposited thereon to fabricate the nuclear fuel structure. The cathode plate may include an upper blade including an electrically conductive material, a lower blade portion connected to the upper blade, and a connection structure configured to secure the lower blade portion to the upper blade while providing electrical continuity. The connection structure may be configured to be disconnected from the lower blade portion to detach the lower blade portion from the upper blade.

Abstract: A nuclear reactor scram control system for a nuclear reactor includes a solenoid pilot valve (SSPV). The SSPV includes a solenoid indicator light electrically coupled to an SSPV solenoid of the SSPV. The solenoid indicator light may be selectively activated based on an energization state of the SSPV solenoid, thereby providing an immediate and visually observable indication of the SSPV energization state. The immediate and visually observable indication of the SSPV energization state may enable quicker and more reliable verification of SSPV solenoid energization state. As a result, operator radiation exposure associated with verification may be reduced, and a risk of inadvertent nuclear reactor scram based on a de-energized SSPV solenoid may be reduced, thus streamlined nuclear reactor operations.

Abstract: A temperature change detection apparatus for monitoring temperature change in various portions of a large space includes a trip logic unit configured to execute a trip operation based on receipt of a trip signal at the trip logic unit; a plurality of temperature sensors each including a sensing portion composed of optical fiber cable and each being configured to generate light information indicating an amount of Brillouin scattering that occurs within the sensing portion; a plurality of monitoring units configured such that each monitoring unit determines a temperature value corresponding to each temperature sensor connected to the monitoring unit based on an amount of Brillouin scattering indicated by the light information generated by each of the connected temperature sensors, an each monitoring unit generates a trip signal when a determined temperature value exceeds a running average by more than a threshold amount.

Abstract: A system and a method for a commercial nuclear repository that turns heat and gamma radiation from spent nuclear fuel into a valuable revenue stream. Gamma radiation from the spent nuclear fuel of the repository may be used to irradiate and sterilize food and other substances. Gamma radiation may also be used to improve the properties of target substances. Additionally, heat decay from the spent nuclear fuel of the repository may be harnessed to heat materials or fluids. The heated fluids may be used, for instance, to produce steam that may make electricity. The heating of working fluids for use in processes, such as heated fluid streams for fermentation or industrial heating, may be transported out of the repository and co-mingled with other heat input, or other fluids.

Abstract: Safety valves accurately control closure and opening of fluid passage through the valve. Valves include a barrier that blocks the fluid until removal only by a high-energy projectile. Following removal and opening, the barrier or the projectile can flow through the valve, which remains open. Bullets, pneumatic pistons, shot, coilgun pellets and any other forceful projectile may impact and remove the barrier. The projectile is actuated with any type of chemical reaction, firing pin, spring release, accelerating circuit, ignition circuit. Catchers in the valve envelop or otherwise retain the projectile or barrier pieces and enter the fluid flow of the opened valve without blocking it. Disruptable barriers include strong but breakable glass plates, thin steel sheets, a rotatable door and other barriers that can withstand potentially over 10,000 psi of fluid pressure while closing the valve. Valves can use circuits to both monitor valve open/closed status and initiate firing the projectile.

Abstract: A system configured to passively filter radioactive materials from a flow may include one or more particulate removal devices; one or more water removal devices; and/or one or more radionuclide removal devices. At least one of the one or more particulate removal devices may mechanically remove particulates of the radioactive materials from the flow. At least one of the one or more water removal devices mechanically may remove water from the flow. At least one of the one or more radionuclide removal devices may remove radioactive aerosols, reactive radioactive gases, or radioactive aerosols and reactive radioactive gases from the flow using engineered filter media. A filter may include a body, including an inlet and an outlet. The body may be configured to store filter media, to contain pressure from gas explosions, and/or to allow the stored filter media to move toward the outlet when pressure at the inlet increases.

Abstract: A system for controlling the power level of a natural circulation boiling water nuclear reactor (NCBWR) may include a heating subsystem for heating feedwater flowing into an annulus of the NCBWR to increase the temperature of recirculation water flowing through the core above a predetermined recirculation water operating temperature. Additionally the system may include a temperature sensor operable to sense the temperature of the feedwater flowing into the annulus. The temperature sensor is communicatively connected to a temperature controller operable to command the heating subsystem to increase the temperature of the feedwater flowing into the annulus to a requested temperature above a predetermined operating temperature of the feedwater flowing into the annulus.

Abstract: A reactor pressure vessel assembly may include a housing surrounding a reactor core, steam separators, and a chimney. Inner surfaces of the chimney and reactor core define a conduit for transporting a two phase flow stream from the reactor core through the chimney to the steam separators. The housing defines an opening. An inner surface of the housing and outer surfaces of the chimney and reactor core define an annulus in fluid communication with the opening and conduit. A feedwater sparger in the housing is connected to the at least one opening and configured to deliver a sub-cooled feedwater into the annulus. A flow barrier structure between the chimney and the steam separators may force mixing between the sub-cooled feedwater and a downcomer fluid from the steam separators. An outer steam separator may be vertically over a portion of the flow barrier structure in a plan view.

Abstract: An apparatus configured to structurally replace a cracked weld in a nuclear plant may include: a first body portion that includes a first gripping portion; a second body portion that includes a second gripping portion; a wedge portion between the first and second body portions; and/or an adjustment portion. The first body portion may be configured to slidably engage the second body portion. The wedge portion may be configured to exert force on the slidably engaged first and second body portions. The adjustment portion may be configured to increase or decrease the force exerted by the wedge portion on the slidably engaged first and second body portions. When the adjustment portion increases the force exerted by the wedge portion on the slidably engaged first and second body portions, a distance between the first and second gripping portions may decrease.

Abstract: A method of facilitating modeling of a system includes receiving, at a processor, an extensible markup language (XML) file corresponding to a piping and instrumentation diagram (PID) of the system; identifying, by the processor, components of the system that are described in the XML file, the XML file including information about attributes of the identified components; storing, by the processor, the information about the attributes of the identified components; and generating, by the processor, a simulation model page using syntax of a simulation modeling software environment, based on the stored information about the attributes of the identified components.

Abstract: Chimneys include several combinable parts usable in nuclear reactors. The parts are modular and removably joinable without destruction for use in directing flow in an operating nuclear reactor and directly fit in storage area during non-operation. Chimney parts are joinable through flanges and connecting structures. Chimney parts may include partitions that divide or direct energetic coolant flow from a nuclear core as well as steam separating and drying structures. The parts each individually fit within storage areas of the nuclear plant, including equipment or buffer pools in the refueling floor of the plant. Methods move the chimney parts between the reactor and storage areas, and multiple parts may be stacked or nested in such moves. Methods are usable underwater and with storage pools to prevent exposure of chimney parts during an outage. During operation, chimneys are usable in place of existing single-piece chimneys.

Abstract: According to at least some example embodiments, a dome collector separation stage includes an inner side wall that defines an inner channel; and an outer side wall that, together with the inner side wall, defines an outer channel, the inner channel being configured to receive a two-phase flow stream (FS) of water and steam, and pass the two-phase FS to the outer channel via inlets included in the inner side wall, the outer channel being configured to separate at least some water from the two-phase FS, and pass moisture-reduced steam out of the steam separator stage via outlets included in the outer side wall.

Abstract: A system for disposing of one or more radioactive components from a nuclear reactor may include a first receptacle configured to receive the one or more radioactive components, a frame configured to support the first receptacle in the nuclear reactor, and a device configured to separate the one or more radioactive components into two or more portions during lowering of the one or more radioactive components into the first receptacle. A method for disposing of one or more radioactive components from a nuclear reactor may include assembling a system for disposing of the one or more radioactive components, and moving the assembled system to an area of a reactor core. A method for disposing of one or more radioactive components from a nuclear reactor may include assembling a system for disposing of the one or more radioactive components in an area of a reactor core.

Abstract: In one embodiment, the steam separation system includes a plurality of steam separators configured to separate liquid from a gas-liquid two-phase flow stream; and a steam dryer system disposed above the steam separators. The steam dryer system includes a plurality of steam dryer bank assemblies and at least one moisture trap. Each of the steam dryer bank assemblies is configured to separate liquid of the gas-liquid two-phase flow stream exiting the steam separators. The moisture trap is disposed next to one of the steam dryer bank assemblies and is configured to remove liquid from the gas-liquid two-phase flow stream.