Ge-hitachi Nuclear Energy Americas LLC

Eric Paul Loewen

Brett Jameson Dooies

Seth Ryan Paul Strege

Nicholas Francis O'Neill

Brian Scott Triplett

Scott L Pfeffer

Maria E Pfeffer

William C Dawn

James P Sineath

Dean D Molinaro

Edwin Wu

Jordan E Hagaman

Chelsea Ann Curtin

David W Webber

Colin Christopher O'Connor

Derek Bass

John F Berger

Robin D Sprague

Joel Patrick Melito

Oscar Lee Meek

Pradip Saha

Theron D Marshall

Scott E Rasmussen

Dana Christine Miranda

William J Garcia

Patrick K Day

Haley Michelle Cowen

Weston Matthew Cundiff

Colin Christopher O'connor

Nicholas Francis O'NEILL

David L Major

Brian S Hunt

Charles Lee Heck

Bradley Wile

David Johnathan Keck

Earl F Saito

Ana Dasilva

Zachary W Kosslow

David Jonathan Keck

Jose Maria Caro

Emma Lebwohl

Kelly Ann Fitzwater

Christopher P Kmiec

Shirly Rodriguez Rojas

Kenneth E Karcher

Haaken Lysne

William Roysdon Murray

Hanying Liu

Nicholas Francis O'neill

Levon Pierre Keusseyan

Colin Christopher O′Connor

Nicholas Francis O′Neill

Seth Strege

Nicholas Francis Oneill

Brian S Triplett

Emma Leora Lebwohl

Westin Matthew Cundiff

Nicholas O'Neill

Nicholas F O'Neill

A sodium-cooled nuclear reactor includes at least one electromagnetic pump assembly and a backflow reduction pipe. The backflow reduction pipe may include an inlet, an outlet, at least one tubular section having a first length and a first diameter, and at least one fluid diode section between the inlet and the outlet.

Piping enhancement for backflow prevention in a multiple loop, metal cooled nuclear reactor system

A liquid metal-cooled nuclear reactor includes, within a reactor pressure vessel having a reactor core, a multistage annular linear induction pump (ALIP) configured to circulate liquid metal coolant through the reactor core. The multistage ALIP includes multiple sets of induction coils that at least partially define separate, respective stages of the multistage ALIP. The multiple sets of induction coils are configured to be electrically connected to separate, respective polyphase power supplies, such that the stages of the multistage ALIP are configured to be controlled independently of each other to adjustably control a flow of liquid metal coolant through the reactor core based on independent control of the multiple polyphase power supplies.

Multistage annular linear induction pump for nuclear reactors

The apparatus includes a flowmeter coupled a surface exposed to a flow channel. The flowmeter monitors a flow of coolant. The flowmeter includes a first temperature sensor that generates first temperature data based on measuring a first temperature of a first flowstream, a heating element coupled to the first temperature sensor where the heating element applies heat to the first temperature sensor through an interface, a second temperature sensor generates second temperature data based on measuring a second temperature of a second flowstream, the second temperature sensor being spaced apart from the heating element, and the second temperature sensor being at least partially insulated from the heating element so the second temperature data generated by the second temperature sensor is independent of heat generated by the heating element. A processor calculates a flowrate of the coolant based on the second temperature data and a temperature of the coolant fluid.

Apparatus with flow assembly including temperature sensors and heating element

Nozzles mix coolant from different sources together in an outlet to prevent differences in coolant output. Different flow path configurations are useable in the nozzle, including a multiple-path configuration with flows from different sources jacketed or concentrically arranged around flows from other sources. Swirl vanes may be installed in the nozzle to impart mixing or filtering the fluid flow. Diffusers may be used to passively suction or accelerate flow and mixing the same like a jet pump. Nozzles can be combined with filtration systems like trap filters that capture debris based on a momentum difference between the denser debris and fluid. Filters can use magnetic, adhesive, or porous materials to capture debris without blocking a flow path. Filters can be disengaged, such as when clogged, such that coolant flows around the system. Nozzles can be installed on feedwater sparger assemblies in varying manner to distribute coolant from multiple nozzles.

Intermixing feedwater sparger nozzles and methods for using the same in nuclear reactors

Steam generators in power plants exchange energy from a primary medium to a secondary medium for energy extraction. Steam generators include one or more primary conduits and one or more secondary conduits. The conduits do not intermix the mediums and may thus discriminate among different fluid sources and destinations. One conduit may boil feedwater while another reheats steam for use in lower and higher-pressure turbines, respectively. Valves and other selectors divert steam and/or water into the steam generator or to other turbines or the environment for load balancing and other operational characteristics. Conduits circulate around an interior perimeter of the steam generator immersed in the primary medium and may have different cross-sections, radii, and internal structures depending on contained. A water conduit may have less flow area and a tighter coil radius. A steam conduit may include a swirler and rivulet stopper to intermix water in any steam flow.

Systems and methods for steam reheat in power plants

The method includes configuring a nuclear reactor to at least partially mitigate liquid metal coolant backflow in the nuclear reactor in response to an at least partial failure of a primary electromagnetic pump (EMP) within a reactor pressure vessel of the nuclear reactor, the nuclear reactor being liquid metal-cooled, the primary EMP configured to circulate liquid metal coolant through at least a reactor core of the nuclear reactor, the configuring including, installing a backflow EMP within the reactor pressure vessel, such that when selectively activated, the backflow EMP at least partially mitigates liquid metal coolant backflow through the primary EMP.

Method of configuring liquid metal-cooled nuclear reactor with backflow electromagnetic pump (EMP)

Vibration-based flowmeters are useable in inaccessible nuclear reactor spaces. Pipe-organ-type flowmeters include a passage with an opening constricted, and subsequent widening section. An extension and outlet that create turbulence in the flow at the outlet create a standing wave and vibration in the extension and/or entire flowmeter. A flow rate of the fluid through the flowmeter can be calculated using length of the passage and/or known properties of the fluid. Multiple flowmeters of customized physical properties and types are useable together.

Vibration-based acoustic flowmeters with a vibration detector detecting vibrations caused by a standing wave

A nuclear plant including a nuclear reactor and a natural circulation air cooling system configured to provide cooling of the nuclear reactor based on circulating ambient air from an air inlet opening to absorb nuclear reactor rejected heat through an outlet air opening, due to natural circulation of said ambient air induced by the ambient air absorbing said rejected heat, may further include a pile structure covering at least one opening of the air inlet opening or the air outlet opening. The pile structure may include a pile of packing objects covering the at least one opening, such that the at least one opening is obscured from direct exposure to the ambient environment by the pile of the packing objects.

Natural circulation heat removal system for a nuclear reactor with pile structure

Casks shield materials and passively remove heat via heat transport paths from deep inside to outside the cask. The transport path may be heat pipes and conductive rods that are non-linear so that radiation is always shielded by the cask. A damper may surround an end of the heat transport path to control heat loss from the cask. A jacket of fluid or meltable material that conducts heat by convection may surround stored materials ensure an even temperature within the cask, and the heat transport path may absorb heat from the jacket. Casks are useable to safely store, transport, and dispose of any sensitive or heat-generating material. Casks may be opened or closed to simultaneously load and offload materials at a consistent operating temperature provided by heaters in the cask.

Passive heat removal casks and methods of using the same

Damper systems selectively reduce coolant fluid flow in nuclear reactor passive cooling systems, including related RVACS. Systems include a damper that blocks the flow in a coolant conduit and is moveable to open, closed, and intermediate positions. The damper blocks the coolant flow when closed to prevent heat loss, vibration, and development of large temperature gradients, and the damper passively opens, to allow full coolant flow, at failure and in transient scenarios. The damper may be moveable by an attachment extending into the coolant channel that holds the damper in a closed position. When a transient occurs, the resulting loss of power and/or overheat causes the attachment to stop holding the damper, which may be driven by gravity, pressure, a spring, or other passive structure into the open position for full coolant flow. A power source and temperature-dependent switch may detect and stop holding the damper closed in such scenarios.

Methods for airflow control in reactor passive decay heat removal using a damper

The system for storage includes spent nuclear fuel arranged in a drift and at least one first mechanical structure configured to cause a target material to move in the drift. The at least one first mechanical structure is configured to at least assist in actively controlling an exposure rate of the target material to the spent nuclear fuel while the target material is being exposed to the spent nuclear fuel. The system includes at least one second mechanical structure configured to remove the target material from the drift after the target material is exposed to the spent nuclear fuel.

System for spent nuclear fuel storage

An electro-technical device, includes an input electrical connection supplied with an input signal and electrically isolated from an output electrical connection. A bar magnet is pivotally mounted on a pedicel between the input electrical connection and the output electrical connection. A pair of coils disposed on opposite sides of the bar magnet and each being supplied with an electronic signal from a sensor, the bar magnet being responsive to an electromagnetic filed generated by the pair of coils to cause the bar magnet to contact the input electrical connection and the output electrical connection and complete a circuit and send out a control signal.

Passive electrical component for safety system shutdown using Gauss' law of magnetism

An electro-technical device includes a first housing portion electrically isolated from a second housing portion with a point source being disposed within the first housing portion. A movable conductor is connected to the first portion and is responsive to an electric field generated by the point source to cause the movable conductor to contact the second housing portion to complete a circuit and send out a control signal.

Passive electrical component for safety system shutdown using Gauss' Law

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Wilmington, NC, United States of America

Eric Paul Loewen