Patent classifications
G21C19/07
SYSTEM AND METHOD FOR PREVENTING AND MONITORING LEAKAGE OF WATER FROM TANK LINER
Disclosed are a system and method for preventing and monitoring a leakage of water from a tank liner at a storage tank having: a concrete reservoir; the tank liner made up of a wall liner that is formed by coupling a plurality of first panels and is attached to an inner wall of the concrete reservoir, and a floor liner that is formed by coupling a plurality of second panels, is attached to a floor of the concrete reservoir, and is coupled to the wall liner by welding; a leaking water collecting plate formed by welding a plurality of third panels and inserted between the floor liner and the floor of the concrete reservoir; and an edge leaking water collecting channel buried in an edge of the storage tank and configured to collect leaking water discharged between the floor liner and the leaking water collecting plate.
Handoff methods and assemblies for refueling a nuclear reactor
Systems and methods for refueling a nuclear reactor that has a reactor core in a reactor pool having a plurality of elongated reactor core components, a fuel pool for storing core components, and a transfer channel connecting the fuel pool to the reactor pool. The method includes retrieving a replacement core component from the fuel pool, and securing the replacement core component in a first compartment of a handover assembly in a vertical position. The method also includes retrieving a spent core component from the reactor core, and securing the spent core component in a second compartment of the handover assembly in a vertical position. The replacement core component is retrieved from the first compartment and installed into the reactor core. The spent core component is retrieved from the second compartment and stored in a storage rack in the fuel pool.
Method and apparatus for enhancing the electrical power output of a nuclear reactor power generation system
A panel that uses the gamma radiation emitted by fission to produce electrical power. The panel includes layers of a metal with a relatively high atomic number (Z), that form an emitter, a high temperature electrical resistor, and an electrical conductor with a relatively low Z value, that forms a collector. The gamma radiation emitted during the fission process produces Compton and photoelectrical electrons in the layer of the Emitter located between the reactor Baffle and the fuel assemblies. The electrons that have sufficient energy to penetrate the resistor layer between the emitter layer and the collector layer will be stopped in the collector. This creates a substantial voltage difference between the emitter and the collector. This voltage difference may be used to produce significant electric power both during reactor operations and with the reactor shutdown to meaningfully augment the electricity produced by the turbine generators.
Modular water purification system for nuclear power plants
A modular water purification system for a nuclear power plant includes a plurality of modules that may be selectively connected together directly or through the use of intermediary adapters in a plurality of arrangements. The modules may include a pump module, a FOSAR module, a particulate filtration module, a cross-flow filtration module, a degasification module, and/or a demineralization module, among other possible modules. The modules may have common interfaces so that they can be interconnected (directly or through intermediary adapters) in a variety of configurations for different purposes within the context of the nuclear power plant (e.g., filtering pool water; collecting large objects via vacuuming). Various modules may have form factors and/or mounting structures that are similar enough to the fuel assemblies of the plant that (1) the plant's fuel assembly handling equipment can grab, move, and reposition the modules, and/or (2) the modules may be stored in the fuel pool's storage rack.
Modular water purification system for nuclear power plants
A modular water purification system for a nuclear power plant includes a plurality of modules that may be selectively connected together directly or through the use of intermediary adapters in a plurality of arrangements. The modules may include a pump module, a FOSAR module, a particulate filtration module, a cross-flow filtration module, a degasification module, and/or a demineralization module, among other possible modules. The modules may have common interfaces so that they can be interconnected (directly or through intermediary adapters) in a variety of configurations for different purposes within the context of the nuclear power plant (e.g., filtering pool water; collecting large objects via vacuuming). Various modules may have form factors and/or mounting structures that are similar enough to the fuel assemblies of the plant that (1) the plant's fuel assembly handling equipment can grab, move, and reposition the modules, and/or (2) the modules may be stored in the fuel pool's storage rack.
Leakage testing device for seal verification by penetrant inspection of a nuclear fuel assembly located in a cell of a storage rack
A leakage testing device for testing leakage of a nuclear fuel assembly (18) by sipping. The device includes a collection assembly (32) that is configured to close an upper end (24A) of a cell (24) of a storage rack (22) for storing nuclear fuel assemblies discharged from a nuclear reactor (4). The closing prevents water contained in the cell from escaping via the upper end of the cell. The collection assembly is configured to collect products containing possible fission products released by a nuclear fuel assembly contained in the cell.
Radioactive waste repository when contacted by water provides borates that absorb neutrons
A container holds radioactive material. A sub-criticality controller protects the radioactive material from reaching a criticality from contact with the water. The sub-criticality controller includes a metallic composition having at least one metal component and at least one borate component bonded to the at least one metal component. The metallic composition forms borates when the metallic composition contacts the water.
Reactor containment building spent fuel pool filter vent
A nuclear reactor containment atmospheric filter system includes dedicated piping, valves, a control system, and a chemical injection system. An outlet of the piping can release atmospheric effluent from a reactor containment vessel into a lower portion of a spent fuel pool. The chemical injection system can release a chemical into the spent fuel pool to facilitate a reaction with the released atmospheric effluent. The reaction can assist in neutering deleterious environmental impact of the atmospheric effluent. The filter system can filter and cool contaminated air and steam vapor released from the reactor containment vessel, and prevent vessel overpressure and radioactive release.
Reactor containment building spent fuel pool filter vent
A nuclear reactor containment atmospheric filter system includes dedicated piping, valves, a control system, and a chemical injection system. An outlet of the piping can release atmospheric effluent from a reactor containment vessel into a lower portion of a spent fuel pool. The chemical injection system can release a chemical into the spent fuel pool to facilitate a reaction with the released atmospheric effluent. The reaction can assist in neutering deleterious environmental impact of the atmospheric effluent. The filter system can filter and cool contaminated air and steam vapor released from the reactor containment vessel, and prevent vessel overpressure and radioactive release.
Method for housing nuclear reactor modules
An in-core instrumentation system for a reactor module includes a plurality of in-core instruments connected to a containment vessel and a reactor pressure vessel at least partially located within the containment vessel. A reactor core is housed within a lower head that is removably attached to the reactor pressure vessel, and lower ends of the in-core instruments are located within the reactor core. The in-core instruments are configured such that the lower ends are concurrently removed from the reactor core as a result of removing the lower head from the reactor pressure vessel.