Ge-Hitachi Nuclear Energy Americas LLC

James P Sineath

Eric Paul Loewen

William C Dawn

Dean D Molinaro

Robin D Sprague

Oscar Lee Meek

Joel Patrick Melito

Theron D Marshall

William J Garcia

Patrick K Day

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

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

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

Systems and methods for airflow control in reactor passive decay heat removal

Vibration-based flowmeters are useable in inaccessible nuclear reactor spaces. Flowmeters include an extension that blocks fluid flow in a path and a detector that detects vibrations caused by vortex shedding in the fluid flow around the extension. The detected frequency of the vibrations determines the flow rate. A Strouhal number may be used to calculate the flow speed using extension surface diameter and detected vortex shedding frequency. Several extensions may cover a range of frequencies and flow speeds. 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.

Acoustic flowmeters and methods of using the same

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Summerville, SC, United States of America

James P Sineath