Ge-Hitachi Nuclear Energy Americas LLC

Phillip Glen Ellison

John Robert Bass

Adrian M Mistreanu

John S Bennion

Bulent Alpay

James Scott Bowman

Bobby Glen Malone

Michael James

Robert Joseph Ginsberg

Jose Maria Caro

Necdet Kurul

Mark W Siewert

Richard M Rogers

Edward C Andersen

Robert Henry Cowen

Michael James Barbaretta

Jin Yan

John R Bass

According to at least some example embodiments, a dome collector separation stage includes an inner side wall that defines an inner channel; and an outer side wall that, together with the inner side wall, defines an outer channel, the inner channel being configured to receive a two-phase flow stream (FS) of water and steam, and pass the two-phase FS to the outer channel via inlets included in the inner side wall, the outer channel being configured to separate at least some water from the two-phase FS, and pass moisture-reduced steam out of the steam separator stage via outlets included in the outer side wall.

Apparatuses for steam separation, and nuclear boiling water reactors including the same

A steam separation system includes a standpipe configured to receive a gas-liquid two-phase flow stream and a diffuser configured to receive the gas-liquid two-phase flow stream from the standpipe. The diffuser includes a swirler configured to separate the gas-liquid two-phase flow stream. The swirler includes a plurality of swirler vanes and a straightener structure. The straightener structure includes a hub. The plurality of swirler vanes is mounted radially around the hub, and a straightener extends in an upward direction from the hub. The system also includes a separation barrel configured to receive the gas-liquid two-phase flow stream from the swirler. The separation barrel includes a rifled channel having orifices along an inner surface thereof. The plurality of swirler vanes is tuned with the rifled channel, such that an angle of each of the plurality of vanes corresponds to an angle of the rifled channel.

Steam separator and nuclear boiling water reactor including the same

In one embodiment, the steam separation system includes a plurality of steam separators configured to separate liquid from a gas-liquid two-phase flow stream; and a steam dryer system disposed above the steam separators. The steam dryer system includes a plurality of steam dryer bank assemblies and at least one moisture trap. Each of the steam dryer bank assemblies is configured to separate liquid of the gas-liquid two-phase flow stream exiting the steam separators. The moisture trap is disposed next to one of the steam dryer bank assemblies and is configured to remove liquid from the gas-liquid two-phase flow stream.

Steam separation system and nuclear boiling water reactor including the same

A system and a method for a passive containment vent system for a Boiling Water Reactor (BWR). The system is capable of venting and scrubbing a gaseous discharge from the primary containment of the BWR over a prolonged period of time leading up to or following a serious plant accident, without the need for monitoring by on-site plant personnel. External electrical power is not required (following initial activation of the system) in order to operate the containment vent system. The system may protect the integrity of primary containment during and following the serious plant accident.

Containment vent system with passive mode for boiling water reactors (BWRS), and method thereof

In one embodiment, the steam separator includes a standpipe configured to receive a gas-liquid two-phase flow stream, and a first swirler configured to receive the gas-liquid two-phase flow stream from the standpipe. The first swirler is configured to separate the gas-liquid two-phase flow stream. The first swirler includes a direct flow portion and an indirect flow portion. The direct flow portion has a direct flow channel for permitting direct flow of the gas-liquid two-phase flow stream through the first swirler, and the indirect flow portion has at least one indirect flow channel defined by at least one vane in the first swirler for providing an indirect flow of the gas-liquid two-phase flow stream through the first swirler.

Swirler, steam separator including the swirler, and nuclear boiling water reactor including the same

A post-accident fission product removal system may include an air mover, a filter assembly, and/or an ionization chamber. The air mover may be configured to move contaminated air through the filter assembly to produce filtered air. The ionization chamber may be connected to the filter assembly. The ionization chamber may include an anode and a cathode. The ionization chamber may be configured to receive the filtered air from the filter assembly and to ionize and capture radioisotopes from the filtered air to produce clean air.

Post-accident fission product removal system and method of removing post-accident fission product

A method and apparatus for providing an alternative remote spent fuel pool cooling system for the spent fuel pool. The cooling system is operated to cool the spent fuel pool in the event of a plant accident when normal plant electricity is not available for the conventional fuel pool cooling and cleanup system, or when the integrity of the spent fuel has been jeopardized. The cooling system is operated and controlled from a remote location, which is ideal during a plant emergency.

Method and apparatus for an alternative remote spent fuel pool cooling system for light water reactors

An embodiment of the present invention takes the form of a system that may reduce the level of flow-induced vibration (FIV) experienced by a jet pump assembly or other similar object within a pressure vessel. Essentially, an embodiment of the present invention may reduce the slip-joint leakage, which may be a cause of the FIVs, by adding a flow-limiting component to an outlet of the slip joint. This component may take the form of a collar, channel, and/or other component that may be connectable to a component of the jet pump assembly. After installation, an embodiment of the present invention may lower the amplitude of, and/or change the frequency of, the FIVs experienced by the jet pump assembly.

System for dampening vibration

A jet pump assembly according to an example embodiment of the present invention includes an inlet body arranged in proximity with a throat structure so as to provide an entrainment entrance between a discharge end of the inlet body and the throat structure. A drive flow of a motive fluid is supplied at a first velocity to the inlet body and is discharged through at least one nozzle at a higher second velocity, thereby creating a pressure drop in the throat structure. The pressure drop facilitates a first entrained flow of suction fluid into the entrainment entrance and a second entrained flow of suction fluid through at least one channel passing through the inlet body. The at least one channel is configured such that the second entrained flow is isolated from the drive flow while passing through the inlet body.

Jet pump assembly having increased entrainment flow

A boiling water nuclear reactor (BWR) multi-stage jet pump mixer assembly according to a non-limiting embodiment of the present invention may include at least one nozzle disposed above a first throat structure which is arranged within a second throat structure. The multi-stage jet pump mixer assembly is configured such that when a drive flow is discharged from the nozzle into the first throat structure, a first suction stage occurs in that a first entrained flow is drawn into the first entrainment entrance and forms a mixed flow. The mixed flow exiting the first throat structure then induces a second entrained flow into the second entrainment entrance during a second suction stage. By employing a multi-stage approach, jet pump efficiency may be improved.

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Wilmington, NC, United States of America

Phillip Glen Ellison