Patent application number | Description | Published |
20120159876 | SEISMIC AND IMPACT MITIGATION DEVICES AND SYSTEMS - Systems mitigate structural damage by selectively engaging energy-absorbing structures only during impact events, including aircraft impacts. Systems include lateral dampening devices and/or seismic bearings between a structure and its foundation. Lateral dampening devices include a restorative member and/or reactive member configured to rigidly join the structure and the foundation and dampen reactive movement after the structure moves toward the foundation during an impact event. Seismic bearings include a top plate connected to the structure, a bottom plate connected to the foundation, and a resistive core between the top plate that dampens relative movement between the structure and the foundation. Seismic bearings may include a capture assembly that rigidly joins and dampens reactive movement between the structure and the foundation during an impact event. The structure may further include a ledge into which the top plate seats and dampens reactive movement between the structure and the foundation during an impact event. | 06-28-2012 |
20130167531 | VAPOR FORMING APPARATUS, SYSTEM AND METHOD FOR PRODUCING VAPOR FROM RADIOACTIVE DECAY MATERIAL - Example embodiments include a vapor forming apparatus, system and/or method for producing vapor from radioactive decay material. The vapor forming apparatus including an insulated container configured to enclose a nuclear waste container. The nuclear waste container includes radioactive decay material. The insulated container includes an inlet valve configured to receive vapor forming liquid. The radioactive decay material transfers heat to the vapor forming liquid. The insulated container also includes an outlet valve configured to output the vapor forming liquid heated by the radioactive decay material. | 07-04-2013 |
20130272468 | IN-SITU AND EXTERNAL NUCLEAR REACTOR SEVERE ACCIDENT TEMPERATURE AND WATER LEVEL PROBES - A system for monitoring a state of a reactor core in a nuclear reactor may include an internal monitoring device located inside the reactor core, the internal monitoring device including one or more internal sensor arrays configured to take measurements of conditions of the reactor core at different vertical regions within the reactor core to generate internal measurement data; an external monitoring device located in the reactor structure outside the reactor core, the external monitoring device including one or more external sensor arrays configured to take measurements of conditions of the reactor core at positions outside the reactor core corresponding the plurality of different vertical regions within the reactor core to generate external measurement data, and a transmitter configured to wirelessly transmit the external measurement data; and a receiver station configured to determine a state of the reactor core based on the external and internal measurement data. | 10-17-2013 |
20130272469 | DEVICE AND METHOD FOR REACTOR AND CONTAINMENT MONITORING - A device for monitoring a reactor during normal and off-normal operating conditions may include a case formed of a rigid material, the case including a shielding layer configured to insulate an internal portion of the device from external heat and radiation; a coupling unit configured to adhere the case to a surface location of a reactor; a sensing unit configured to generate environmental measurements by measuring environmental conditions in the vicinity of the reactor; a data processing unit configured to generate measurement data by processing the environmental measurements; a transmitter configured to transmit the measurement data externally from the device; and a power unit configured to power the device independently of an external power source. | 10-17-2013 |
20130277228 | METHOD FOR CORIUM AND USED NUCLEAR FUEL STABILIZATION PROCESSING - A method for stabilizing a nuclear material may include electrolytically reducing the nuclear material in a first molten salt electrolyte of an electroreducer to produce a reduced material. A reducer waste may accumulate in the first molten salt electrolyte as a byproduct of the electroreduction. After the electroreduction, the reduced material may be electrolytically dissolved in a second molten salt electrolyte of an electrorefiner to produce a purified metal product on a refiner cathode assembly of the electrorefiner. As a result of the electrorefining, a first refiner waste may accumulate in the second molten salt electrolyte and a second refiner waste may accumulate in a refiner anode assembly of the electrorefiner. The reducer waste from the electroreducer and the first refiner waste from the electrorefiner may be converted into a ceramic waste form, while the second refiner waste from the electrorefiner may be converted into a metallic waste form. | 10-24-2013 |
20130287161 | HEAT REMOVAL SYSTEM AND METHOD FOR A NUCLEAR REACTOR - In one embodiment, the heat removal system includes a storage tank configured to store a heat transfer medium, a transfer system configured to selectively transfer the heat transfer medium from the storage tank to the nuclear reactor, and a delivery system operationally connected to the transfer system. The delivery system is configured to deliver the heat transfer medium to a suppression pool room of the nuclear reactor. The suppression pool room houses a suppression pool. | 10-31-2013 |
20130287163 | FUEL BUNDLE FOR A LIQUID METAL COOLED NUCLEAR REACTOR - In one embodiment, the fuel bundle for a liquid metal cooled reactor includes a channel, a nose assembly secured to a lower end of the channel, and a plurality of fuel rods disposed within the channel. At least one of the fuel rods has at least one guard ring surround the fuel rod and spacing the fuel rod from adjacent fuel rods. | 10-31-2013 |
20130301767 | SYSTEM AND METHOD FOR A COMMERCIAL SPENT NUCLEAR FUEL REPOSITORY TURNING HEAT AND GAMMA RADIATION INTO VALUE - 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. | 11-14-2013 |
20130308742 | FUEL BUNDLE FOR A LIQUID METAL COOLED NUCLEAR REACTOR - In one embodiment, a fuel bundle for a liquid metal cooled reactor includes a channel, a nose assembly secured to a lower end of the channel, a plurality of fuel rods disposed within the channel, and an internal mixer disposed within the channel above the plurality of fuel rods. The internal mixer includes peripheral flow control members and interior flow control members. The peripheral flow control members are located near walls of the channel, and the interior flow control members are located towards a longitudinal center of the housing. At least one of the peripheral flow control members is configured to direct liquid metal flowing through the channel towards an interior of the channel, and at least one of the interior flow control members is configured to direct liquid metal flowing through the channel away from the interior of the channel. | 11-21-2013 |
20130341555 | METHOD OF FABRICATING LIQUID-METAL COOLANTS FOR NUCLEAR REACTORS - A method of fabricating a liquid-metal coolant includes adding nanoparticles to the liquid-metal coolant to change neutronic properties of the liquid-metal coolant. The nanoparticles have neutronic properties different from that of the liquid-metal coolant. | 12-26-2013 |
20140005462 | SYSTEM AND METHOD FOR PROCESSING AND STORING POST-ACCIDENT COOLANT | 01-02-2014 |
20140069468 | METHODS OF CLEANING A SUBMERGED SURFACE USING A FLUID JET DISCHARGING A LIQUID/GAS COMBINATION - A method of cleaning a submerged surface covered by a liquid medium includes injecting a cleaning liquid with a submerged fluid jet through the liquid medium at the submerged surface. The method may also include introducing at least one of a non-reactive gas and a reactive gas with the cleaning liquid through the submerged fluid jet. | 03-13-2014 |
20140073829 | METHODS AND APPARATUSES FOR STABILIZING FUEL CONTAINING REACTIVE SODIUM METAL - A method of stabilizing a fuel containing a reactive sodium metal may include puncturing a cladding of a fuel pin enclosing the fuel containing the reactive sodium metal to form an injection passage and an extraction passage. A reaction gas may be injected into the fuel pin through the injection passage to react with the reactive sodium metal to form a stable sodium compound. A ratio of a product gas and a remaining quantity of the reaction gas exiting the fuel pin through the extraction passage is subsequently measured, wherein the product gas is a reaction product of the reaction gas and the reactive sodium metal within the fuel pin. Once the measured ratio indicates that a reaction between the reaction gas and the reactive sodium metal is complete, the injection passage and the extraction passage are sealed so as to confine the stable sodium compound within the fuel pin. | 03-13-2014 |
20140161218 | RADIOACTIVE CAPTURE SYSTEM FOR SEVERE ACCIDENT CONTAINMENT OF LIGHT WATER REACTORS (LWRS), AND METHOD THEREOF - A system and a method for capturing gaseous, particulate and liquid radioactive material released from primary containment of a Light Water Reactor (LWR) during severe accident conditions. The system includes a below-grade media area, connected to a reactor pressure vessel (RPV) and portions of primary containment, providing varying levels of adsorption/absorption of the radioactive material. The media area is located on-site to offer a passive, self-regulating structure for stabilizing a nuclear reactor. The capture system provides for liquid drainage and gaseous venting of the radioactive material, and a treatment capable of treating the media following stabilization of the reactor. | 06-12-2014 |
20150048612 | SEISMIC SLIP JOINT, SEISMIC-MITIGATING PIPING SYSTEM, AND METHOD OF MITIGATING SEISMIC EFFECTS ON A PIPING SYSTEM - A seismic slip joint may include a fixed sealing surface, a moveable sealing surface, and a solenoid device. The moveable sealing surface is configured to engage the fixed sealing surface to form a sealing interface during a deactivated state. The sealing interface may be a juncture that precludes passage of a fluid therethrough. The solenoid device is configured to switch between the deactivated state and an activated state. The solenoid device may include a piston and a spring structure. The piston is connected to the moveable sealing surface. The spring structure exerts a force on the piston so as to press the moveable sealing surface against the fixed sealing surface to form the sealing interface during the deactivated state. The piston may be configured to compress the spring structure and retract during the activated state so as to separate the moveable sealing surface from the fixed sealing surface. | 02-19-2015 |
20150049852 | SYSTEMS, METHODS, AND FILTERS FOR RADIOACTIVE MATERIAL CAPTURE - 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. | 02-19-2015 |
20150260173 | THERMAL PUMPING VIA IN SITU PIPES AND APPARATUS INCLUDING THE SAME - A thermal-pumping apparatus according to a non-limiting example embodiment may include a first volume structure defining a first inlet opening and a first outlet opening in fluid communication with a first volume, a second volume structure defining a second inlet opening and a second outlet opening in fluid communication with a second volume, and a connection structure joining the first outlet opening of the first volume structure to the second inlet opening of the second volume structure. The connection structure may include a one-directional valve configured to allow fluid flow between the first and second volume structures in one direction only from the first volume of the first volume structure to the second volume of the second volume structure. | 09-17-2015 |
20150318063 | SYSTEMS AND METHODS FOR REDUCING SURFACE DEPOSITION AND CONTAMINATION - Mobile apparatuses move within contaminated fluid to create fluid flows against structures that remove and prevent contaminant deposition on structure surfaces immersed in the fluid. Unsettling flows in water may exceed approximately 2 m/s for radionuclide particles and solutes found in nuclear power plants. Mobile apparatuses include pressurized liquid from a pump or pressurized source that can be chemically and thermally treated to maximize deposition removal. When spraying the pressurized liquid to create the deposition-removing flow, mobile apparatuses may be self-propelled within the fluid about an entire surface to be cleaned. Mobile apparatuses include filters keyed to remove the contaminants moved into the coolant by the flow, and by taking in ambient fluid, enable such filtering of the ambient fluid along with a larger flow volume and propulsion. Propulsion and the pressurized liquid in turn enhance intake of ambient fluid. | 11-05-2015 |
20160027537 | FIBER OPTIC TEMPERATURE SENSING SYSTEM AND METHOD UTILIZING BRILLOUIN SCATTERING FOR LARGE, WELL-VENTILATED SPACES - 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. | 01-28-2016 |
20160053391 | METHODS OF FABRICATING METALLIC FUEL FROM SURPLUS PLUTONIUM - 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). | 02-25-2016 |
Patent application number | Description | Published |
20140175106 | ENTRAINMENT-REDUCING ASSEMBLY, SYSTEM INCLUDING THE ASSEMBLY, AND METHOD OF REDUCING ENTRAINMENT OF GASES WITH THE ASSEMBLY - An entrainment-reducing assembly may include a container configured to hold a liquid. A venting arrangement may extend into an upper portion of the container and be configured to direct condensable and non-condensable gases into the container. A suction structure may extend into a lower portion of the container and be configured to carry out an extraction of excess liquid from the container caused by condensed gases. A deflector may be disposed between the suction structure and the venting arrangement within the container. As a result, an entrainment of uncondensed gases during the extraction of the liquid by the suction structure may be reduced or prevented, thereby protecting the pump from cavitation and failure. | 06-26-2014 |
20140177775 | COOLING SYSTEMS FOR SPENT NUCLEAR FUEL, CASKS INCLUDING THE COOLING SYSTEMS, AND METHODS FOR COOLING SPENT NUCLEAR FUEL - A cooling system for spent nuclear fuel may include a device configured to generate electricity using energy emitted from the spent nuclear fuel. The cooling system may be configured to use the electricity when cooling the spent nuclear fuel. A cask for storage, transport, or storage and transport of spent nuclear fuel may include the cooling system and a container configured to hold the spent nuclear fuel. A method for cooling spent nuclear fuel may include generating electricity using energy emitted from the spent nuclear fuel, and using the electricity in a cooling system for the spent nuclear fuel when cooling the spent nuclear fuel. | 06-26-2014 |
20150194228 | APPARATUSES FOR STABILIZING FUEL CONTAINING REACTIVE SODIUM METAL - A method of stabilizing a fuel containing a reactive sodium metal may include puncturing a cladding of a fuel pin enclosing the fuel containing the reactive sodium metal to form an injection passage and an extraction passage. A reaction gas may be injected into the fuel pin through the injection passage to react with the reactive sodium metal to form a stable sodium compound. A ratio of a product gas and a remaining quantity of the reaction gas exiting the fuel pin through the extraction passage is subsequently measured, wherein the product gas is a reaction product of the reaction gas and the reactive sodium metal within the fuel pin. Once the measured ratio indicates that a reaction between the reaction gas and the reactive sodium metal is complete, the injection passage and the extraction passage are sealed so as to confine the stable sodium compound within the fuel pin. | 07-09-2015 |
20150200021 | PASSIVE SHUTDOWN SYSTEM AND METHOD OF OPERATING A LIQUID METAL COOLED REACTOR USING THE SAME - A passive shutdown system for a liquid metal cooled reactor may include a tube and a neutron absorber within the tube. The tube may be configured to extend through a core of the liquid metal cooled reactor. The tube has an upper end and a lower end. The tube defines a flow path for a liquid metal coolant. The neutron absorber is a mobile structure configured to partially obstruct a flow of the liquid metal coolant within the flow path. A method of operating a liquid metal cooled reactor may involve the use of the passive shutdown system. | 07-16-2015 |
20150200023 | NUCLEAR REACTOR CHIMNEY AND METHOD OF IMPROVING CORE INLET ENTHALPY USING THE SAME - A chimney of a nuclear reactor may include a hollow body with an interior surface and an opposing exterior surface; and a plurality of trip structures on the exterior surface of the hollow body. The chimney may be used in a method of improving a core inlet enthalpy of a nuclear reactor. The method may include interrupting a downward flow of water within a downcomer region of a reactor pressure vessel with a plurality of first trip structures. The downcomer region is an annular space defined by the reactor pressure vessel and a chimney within the reactor pressure vessel. The plurality of first trip structures are disposed on an exterior surface of the chimney. | 07-16-2015 |
20150314240 | SALT FILTRATION SYSTEM AND METHOD OF REMOVING A RADIOACTIVE MATERIAL FROM A GAS USING THE SAME - A method of removing a radioactive material from a gas includes directing the gas through a bed of salt, wherein the gas includes water vapor and the radioactive material. The salt constitutes more than 50 percent by weight of the bed. The method additionally includes condensing the water vapor in the bed and dissolving a portion of the salt to form a salt solution. The method further includes absorbing the radioactive material into the salt solution while a remainder of the gas passes through the bed. A salt filtration system configured to perform the method may be implemented as a pre-filter (or post-filter) to an existing filter unit or as a standalone filter. | 11-05-2015 |
20150351216 | PASSIVE SYSTEM OF POWERING AND COOLING WITH LIQUID METAL AND METHOD THEREOF - Example embodiments disclose a passive system of power and cooling with a liquid metal for a digital system. The passive system may include a digital device operatively coupled to a printed circuit board, a hollow conductive channel body attached to the printed circuit board to circulate the liquid metal to flow within the conductive channel so as to convey electrical power to the digital device during a power loss and transfer heat generated by the digital device, and a tube to deliver the liquid metal in and out of the hollow conductive channel body. A method of operating a liquid metal may involve the use of the passive system. | 12-03-2015 |