Hitachi - GE Nuclear Energy

www.ge-energy.com/nuclear
Ibaraki, Japan

GE Hitachi Nuclear Energy is a provider of advanced reactors and nuclear services. It is located in Wilmington, N.C.. Established in June 2007, GEH is a global nuclear alliance created by General Electric and Hitachi. In Japan, the alliance is Hitachi-GE Nuclear Energy, Ltd. Wikipedia.


Time filter

Source Type

Patent
Hitachi - GE Nuclear Energy | Date: 2017-01-11

Chimneys include several combinable parts useable in nuclear reactors. The parts are modular and removably joinable without destruction for use in directing flow in an operating nuclear reactor and directly fit in storage area during non-operation. Chimney parts are joinable through flanges and connecting structures. Chimney parts may include partitions that divide or direct energetic coolant flow from a nuclear core as well as steam separating and drying structures. The parts each individually fit within storage areas of the nuclear plant, including equipment or buffer pools in the refueling floor of the plant. Methods move the chimney parts between the reactor and storage areas, and multiple parts may be stacked or nested in such moves. Methods are useable underwater and with storage pools to prevent exposure of chimney parts during an outage. During operation, chimneys are useable in place of existing single-piece chimneys.


Patent
Hitachi - GE Nuclear Energy | Date: 2015-10-16

A passive fire response system is configured to suppress a metallic fire. The system includes a reservoir containing an ionic liquid, at least one outlet in communication with the reservoir, a valve arranged between the reservoir and the outlet, a sensor configured to sense at least one of a hydrogen concentration and a temperature and/or heat, and a controller configured to open the valve and release the ionic liquid if an output from the sensor indicates that the at least one of the hydrogen concentration and the temperature equals or exceeds at least one of a threshold hydrogen concentration and a threshold temperature.


An insulated solution injector may include an outer tube and an inner tube arranged within the outer tube. The outer tube and the inner tube may define an annular space therebetween, and the inner tube may define a solution space within. The annular space may be configured so as to insulate the solution within the solution space. As a result, the solution may be kept to a temperature below its decomposition temperature prior to injection. Accordingly, the decomposition of the solution and the resulting deposition of its constituents within the solution space may be reduced or prevented, thereby decreasing or precluding the occurrence of a blockage.


Patent
Hitachi - GE Nuclear Energy | Date: 2017-05-17

Seals 250, 250a, 250b are positioned between abutting nuclear reactor components 102, 118, 120. Example seals 250, 250a, 250b are held in position by gravity, grooves 102a, 102b, retainers 415, direct joining, or other mating structures to seal the abutting components. Compression of example seals 250, 250a, 250b drives the seals 250, 250a, 250b against the joining components, preventing fluid passage therebetween. Example seals 250, 250a, 250b may include a cavity opening 252 to a higher pressure fluid outside the joined components to drive expansion or sealing of the seal. Seals 250, 250a, 250b may have a C-shaped, E-shaped, O-ring, coiled, helical, or other cross-section to provide such a cavity. Example seals 250, 250a, 250b may be flexible materials compatible with radiation and heat encountered in a nuclear reactor. Seals 250, 250a, 250b may be continuous or sectional about the abutment of the components. An annular seal 250b may extend continuously around a perimeter of removably joined core plates, supports 102, shrouds 114, and/or chimney heads 122 and structures. Seals can be installed between and in the components at any time access is available to the components.


Patent
Hitachi - GE Nuclear Energy | Date: 2017-05-17

Devices 100 position inspection and operation tools in a nuclear reactor without use of a bridge or other refueling structure well above the reactor core. Devices 100 can selectively join to in-reactor structures like steam dams 15 through clamping that permits limited movement. Clamps 110 can include one or more rollers 150, 161, 162 that allow for controlled, accurate positioning of the devices 100 relative to the structures. Devices 100 include an extension 190 to which the tools can be affixed. Through selective disengagement of joining structures, devices 100 can move over obstacles on the mounting structure. Devices 100 further include controls 180 so that operators positioned outside the reactor can move the device 100 while mounted on a static structure. The controls 180 can further move the inspection tool in other directions with the extension 190. Devices 100 are useable underwater or submerged in other fluid and may include powering lines or mechanical extensions 180 that permit powering or direct interfacing from operators outside the reactor.


Patent
Hitachi - GE Nuclear Energy | Date: 2017-06-14

A nuclear reactor scram control system 105 for a nuclear reactor includes a solenoid pilot valve (SSPV) 120. The SSPV includes a solenoid indicator light 124-1 to 124-n electrically coupled to an SSPV solenoid 122-1 to 122-n 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.


A method of storing a chimney assembly of a reactor pressure vessel during a nuclear reactor outage may include detaching a chimney barrel with upper chimney partitions therein from a top guide assembly of the reactor pressure vessel. A height of the upper chimney partitions is less than a height of the chimney barrel so as to leave a plenum region in a top section of the chimney barrel. The top guide assembly includes lower chimney partitions therein. The lower chimney partitions are removed from the top guide assembly and inserted into the plenum region of the chimney barrel so as to be on the upper chimney partitions. As a result, the chimney assembly can be stored in a relatively compact form during a reactor outage. The chimney assembly may be a combination of at least the chimney barrel, the upper chimney partitions, and the lower chimney partitions.


Patent
Hitachi - GE Nuclear Energy | Date: 2017-05-31

Chirp waves generated in a transmitting/receiving unit is supplied to ultrasonic sensors (101-1, ..., 101-12). Signals output from the ultrasonic sensors (101-1, ..., 101-12) are supplied to the transmitting/receiving unit and summed in a signal processing/recording unit. The signal processing/recording unit performs mutual correlation processing between the summed signals and the chirp waves and calculates a peak generation time difference. Necessity of exchanging a pipe is determined by calculating and recording the thickness of a pipe from the calculated time difference and calculating a difference between thicknesses measured in the past and the present.


Patent
Hitachi - GE Nuclear Energy | Date: 2017-07-05

Example embodiments disclose an apparatus 10 for inspecting welds in a nuclear reactor. The apparatus may include a body 100, a rotatable pad 105 on the body, a pair of opposing horizontal pads 110a, 110b for moving the device in a vertical direction 120a, 120b, a pair of opposing vertical pads for moving the device in a horizontal direction, and an inspection device 200.


Patent
Hitachi - GE Nuclear Energy | Date: 2017-01-31

[Problem] Provided is an atomic power plant which can be applied to reactors including existing reactors through a simple method and in which a pressure in a primary containment vessel can be restrained from excessively rising in a case where a steam leakage from an exhaust pipe of a stream safety relief valve occurs. [Solution] There are provided a PCV 1, an RPV 3, a main stream line 4, two SRVs 6, an S/P 8, an SRV exhaust pipe 9 which is connected to a quencher 10, a temperature measuring instrument 12 which measures a temperature inside the quencher 10, an SRV controller 13 which controls opening and closing of the SRVs 6. After a lapse of predetermined time from when the SRV 6 is opened, in a case where it is determined that a temperature detected by the temperature measuring instrument 12 is equal to or smaller than a predetermined threshold value, the SRV controller 13 causes the SRV 6 to which the temperature measuring instrument 12 detecting the temperature leads, to be closed and to be prohibited from being opened.

Loading Hitachi - GE Nuclear Energy collaborators
Loading Hitachi - GE Nuclear Energy collaborators