Nuscale Power, LLC

Ross Douglas Snuggerud

Ted Hough

Jose N Reyes, Jr

Tamas Liszkai

Michael Keller

Daniel Ingersoll

Russell Goff

Bill Galyean

Kevin LaFerriere

Jeremiah Doyle

A system for servicing a nuclear reactor module comprises a crane operable to attach to the nuclear reactor module, wherein the crane includes provisions for routing signals from one or more sensors of the nuclear reactor module to one or more sensor receivers.

Servicing a nuclear reactor module

A damping area or 'dash pot' on the upper ends of control rods absorb energy from dropped control rod assemblies without narrowing the diameter of guide tubes. As a result, coolant can freely flow through the guide tubes reducing boiling water issues. The dampening area reduces a separation distance between an outside surface of the control rod and an inside surface of the guide tubes decelerating the control rods when entering a top end of the guide tubes. In another example, the dampening area may be located on a drive shaft. The dampening area may have a larger diameter than an opening in a drive shaft support member that decelerates the drive shaft when dropped by a drive mechanism.

Control rod damping system

A multi-modular power plant includes a plurality of on-site nuclear power modules that generate a power plant output, and a number of power plant systems which operate using electricity associated with a house load of the power plant. A switchyard associated with the power plant may electrically connect the power plant to a distributed electrical grid. The distributed electrical grid may be configured to service a plurality of geographically distributed consumers. Additionally, the switchyard may electrically connect the power plant to a dedicated electrical grid. The dedicated electrical grid may provide electricity generated from the power plant output to a dedicated service load, and the power plant output may be equal to or greater than a combined load of the dedicated service load and the house load. At least a portion of the power plant output may be distributed to both the power plant systems and the dedicated electrical grid.

Multi-modular power plant with dedicated electrical grid

A multi-modular power plant may include a plurality of on-site nuclear power modules configured to generate a power plant output, wherein one or more of the nuclear power modules may be designated as service module units which are configured to generate a first portion of the power plant output. A remainder of the nuclear power modules may be configured to generate a second portion of the power plant output. A number of power plant systems may be configured to operate using electricity associated with a house load of the power plant, wherein the first portion of the power plant output is equal to or greater than the house load. Additionally, a switchyard may be configured to electrically connect the power plant to a distributed electrical grid. The distributed electrical grid may be configured to service a plurality of geographically distributed consumers, and the switchyard may be configured to apply the second portion of the power plant output to the distributed electrical grid. The switchyard may further be configured to apply at least part of the first portion of the power plant output to the power plant systems during a loss of power from the distributed electrical grid.

Multi-modular power plant with off-grid power source

A neutron detection system may include a neutron detection device located outside of a reactor vessel. The neutron detection device may be configured to detect neutrons generated within the reactor vessel. A containment region located intermediate the reactor vessel and a containment vessel may be configured to house a containment medium. A neutron path device may be at least partially located between the reactor vessel and the containment vessel, and the neutron path device may be configured to provide a neutron path to the neutron detection device through a neutron path medium contained within the neutron path device. A neutron attenuation coefficient associated with the neutron path medium may be smaller than a neutron attenuation coefficient associated with the containment medium.

Neutron path enhancement

A cooling system for a reactor module includes a reactor pressure vessel that houses primary coolant and a steam generator that lowers a temperature of the reactor pressure vessel by transferring heat from the primary coolant to a secondary coolant. The steam generator releases at least a portion of the secondary coolant as steam. Additionally, the cooling system includes a containment vessel that at least partially surrounds the reactor vessel in a containment region. The containment region is dry during normal operation of the reactor module. A controller introduces a source of water into the containment region in response to a non-emergency shut down of the reactor module. The source of water is located external to the containment vessel, and the water is introduced into the containment region after the steam generator has initially lowered the temperature of the reactor pressure vessel in response to releasing the steam.

Passive cooling to cold shutdown

A system for managing notifications for a modular power plant that includes one or more power-generation module (PGM) assemblies and one or more common-systems (CS) includes a transceiver that receives data over a network; a display device that displays a graphical display; a memory that stores at least instructions; and a processor device that executes instructions that perform actions. The actions include receiving power plant data over the network that includes signals generated by one or more sensors included in at least one of the PGM assemblies or one of the CS; detecting an event based on the power plant data and one or more notification thresholds; in response to the event, determining a notification type based on the data and the one or more notification thresholds; providing a notification to a user via the graphical display based on the notification type and the event; and enabling the user to acknowledge the notification.

Notification management systems and methods for monitoring the operation of a modular power plant

Systems and methods for servicing a nuclear reactor module are provided. Such systems include a crane that couples to the reactor module. The crane includes a conduit for routing signals from sensors of the reactor module to sensor receivers. The crane includes a drive mechanism to move the reactor module from a reactor bay to a servicing area. The drive mechanism moves the reactor module in a first direction and a second direction that is orthogonal to the first direction. The crane includes a support bracket for mounting sensor signal receivers that receive the signals from the sensors within the nuclear reactor module. The system includes a display to display representations of the signals from the sensors of the nuclear reactor module in a servicing area. Another display displays representations of the signals from the sensors of the nuclear reactor module in an operator area.

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Corvallis, OR, United States of America

Ross Douglas Snuggerud