Ge-Hitachi Nuclear Energy Americas LLC

John Robert Bass

Phillip Glen Ellison

Robert Joseph Ginsberg

Robert A Ayer

Mark W Siewert

Richard M Rogers

Robin D Sprague

Mark A Bergman

Bobby Glen Malone

Curt J Robert

Ted Gordon Bahensky

Sean Wilson Miers

Jin Yan

Phillip G Ellison

Bobby Malone

A pump leakage mitigation device includes one or more clamp arms on an outer surface of a pump that can be driven by a biasing element to seat against a shaft of the pump to seal or reduce fluid flow through a breakdown of the pump. The biasing element engages only at threshold temperatures, such as those associated with breakdown orifice failure when additional sealing may be necessary. Clamp arms of any number and shape can be used to achieve the desired seal and based on the pump geometry. A sealant surface and/or keeping mechanism are useable with the leakage mitigation device to enhance fluid flow blockage throughout a pump failure transient scenario. Pump leakage mitigation devices are installed on an outside of a variety of different pump types and can thus be installed, actuated, manipulated, disengaged, and/or removed without having to destroy or disassemble the pump.

Methods and apparatuses for pump sealing during leakage events

A nuclear reactor scram control system for a nuclear reactor includes a solenoid pilot valve (SSPV). The SSPV includes a solenoid indicator light electrically coupled to an SSPV solenoid of the SSPV. The solenoid indicator light may be selectively activated based on an energization state of the SSPV solenoid, thereby providing an immediate and visually observable indication of the SSPV energization state. The immediate and visually observable indication of the SSPV energization state may enable quicker and more reliable verification of SSPV solenoid energization state. As a result, operator radiation exposure associated with verification may be reduced, and a risk of inadvertent nuclear reactor scram based on a de-energized SSPV solenoid may be reduced, thus streamlined nuclear reactor operations.

Nuclear reactor scram control system

An apparatus for controlling movement of a first component integrated with a second component may include a first clamp configured to engage the first component, a second clamp configured to engage the second component, and a plurality of connectors configured to connect the first and second clamps. The connectors may allow movement of the first clamp relative to the second clamp in a first direction between the first and second clamps. The connectors may limit movement of the first clamp relative to the second clamp in a second direction perpendicular to the first direction.

Apparatuses and methods for controlling movement of components

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 temperature sensor array includes several temperature sensors at different positions for installation within an instrumentation tube of a nuclear reactor. The temperature sensors measure temperature at multiple axial positions of the nuclear reactor, and plant operators are able to access and interpret this measurement data. Temperatures associated with vessel coolant boiling or loss and/or fuel damage can be detected by the temperature sensors to permit more direct determinations of core fluid levels. Multiple temperature sensor arrays permit vessel fluid levels and conditions to be measured at multiple core locations.

Methods and apparatuses for monitoring nuclear reactor core conditions

A method and apparatus for providing an alternative cooling system for the suppression pool of a Boiling Water Reactor (BWR) nuclear reactor. The cooling system is operated to cool the suppression pool in the event of a plant accident when normal plant electricity is not available for the conventional residual heat removal system and pumps. The cooling system may also be used to supplement the cooling of the suppression pool via the residual heat removal system. The cooling system is operated and controlled from a remote location, which is ideal during a plant emergency.

Method and apparatus for an alternative suppression pool cooling for boiling water reactors

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.

Multi-stage jet pump mixer assembly

Slip joint clamps are installed against guide ears of diffusers at jet pump slip joints. Clamps may prevent vibration and/or movement in the slip joint while not being rigidly attached to the diffuser. Clamps include a compression flipper pressing against a guide ear of the diffuser in a substantially radial direction, a biasing member between the compression member and guide ear that presses the flipper against the guide ear, and supporting structures that hold the flipper and biasing member to the inlet mixer about the guide ear. Systems of slip joint clamps are installed against several guide ears of a single diffuser. Each clamp may radially stabilize the diffuser and inlet mixer while permitting upward relative movement of the inlet mixer. Placement and tensioning of clamps in such systems may be varied so as to prevent or reduce vibrations and/or oscillations between an inlet mixer and diffuser.

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Wilmington, NC, United States of America

John Robert Bass