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Corvallis, OR, United States

Patent
NuScale Power Inc. | Date: 2014-05-28

A steam generator tube probe includes a probe head comprising an electronic probe coupled between a proximal portion of the head that is configured for entry into a steam generator tube and a distal portion of the head; and a probe shaft coupled to the distal portion of the shaft and comprising a flexible metallic conduit that comprises a plurality of interlocking portions, each interlocking portion moveably affixed to at least one adjacent interlocking portion.


Patent
NuScale Power Inc. | Date: 2014-04-16

A heat transfer system includes a plenum configured to provide a secondary side fluid such as feedwater to a plurality of heat transfer tubes from a primary side fluid, and a tube sheet coupled to the plurality of heat transfer tubes. An orifice plate is mounted within the plenum and located adjacent to the tube sheet, and one or more orifice devices are supported by the orifice plate and are configured for insertion into or sealing against the plurality of heat transfer tubes. The one or more orifice devices may include center flow orifices, and/or rectangular or helical shaped transition stepped annular flow orifices, and an insertion of a number of the transition steps into the plurality of heat transfer tubes may determine a corresponding pressure drop of the secondary side fluid in the heat transfer system.


Patent
NuScale Power Inc. | Date: 2014-04-25

A tube support assembly for a steam generator system is disclosed herein, including a sheet or support bar configured to support a plurality of heat transfer tubes of the steam generator system and a set of projections extending from a surface of the sheet or support bar. A distance that the set of projections extend from the surface of the sheet or support bar may be greater than, or equal to, an external diameter of a heat transfer tube. The adjacent tubes of the plurality of tubes may be separated from each other by one or more projections.


Patent
NuScale Power Inc. | Date: 2014-02-18

A nuclear reactor control rod drive assembly includes a control rod drive mechanism coupled to a drive shaft and operable to bi-directionally urge the drive shaft through a portion of an inner volume of a reactor vessel at a first force; a control rod manifold coupled to the drive shaft; a plurality of control rods coupled to the control rod manifold, the plurality of control rods adjustable among a plurality of positions within the inner volume of the reactor vessel based on operation of the control rod drive mechanism; and at least one variable strength joint positioned between the control rod drive mechanism and the plurality of control rods.


Patent
NuScale Power Inc. | Date: 2015-07-02

A system for measuring flow rate within a volume includes one or more transmission devices that transmit one or more signals through fluid contained within the volume. The volume may be bounded, at least in part, by an outer structure and by an object at least partially contained within the outer structure. A transmission device located at a first location of the outer structure transmits a first signal to a second location of the outer structure. A second signal is transmitted through the fluid from the second location to a third location of the outer structure. The flow rate of the fluid within the volume may be determined based, at least in part, on the time of flight of both the first signal and the second signal.

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