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7222058 Method of modeling and sizing a heat exchanger  
A method of modeling a heat exchanger is disclosed and comprises assigning input temperatures, assumed output temperatures, and a set of flow rates, inputting the parameters into a set of equations...
7218068 Power source for re-circulation pump and method of controlling the same  
A variable-voltage variable-frequency power source for an electric motor that drives a re-circulation pump for a boiling water nuclear reactor. The power source has a semiconductor electric power...
7215729 Fuel assembly and nuclear reactor  
A resistance member (e.g., fuel holding portion of the lower tie plate) is provided at the lower end of the fuel assembly. Provision is made of a coolant ascending path in which said water rods...
7002443 Method and apparatus for cooling magnetic circuit elements  
An apparatus and method for providing cooling to a magnetic circuit element having a magnetic core disposed around a centrally located core support member having at least one core support member...
6980621 Main steam system around nuclear reactor  
A main steam system around a nuclear reactor which comprises two main steam nozzles in a reactor pressure vessel, each of the main nozzles being disposed at a symmetrical position with respect to a...
6909765 Method of uprating an existing nuclear power plant  
An improved method of increasing the power output of an existing nuclear power plant includes increasing the thermal power output of the plant's nuclear island and constructing of an auxiliary BOP...
6673846 Handling of a catalyst  
This invention relates to methods of minimizing catalyst degradation during the handling of a catalyst used in a slurry phase reactor. The methods include catalyst handling steps such as catalyst...
6643348 Steam turbine control device of nuclear power plant  
A steam turbine control device. A main steam system runs between a nuclear reactor and a steam turbine and includes a main steam isolation valve (MSIV), a main steam control valve, and a turbine...
6606366 Nuclear power plant having steam turbine controller  
There is provided a nuclear power plant having a steam turbine controller. The nuclear power plant includes a main steam supply system and a turbine by-pass system. The main steam supply system...
6594333 Thermal load reducing system for nuclear reactor vessel  
The present invention is used to reduce thermal load itself, being the cause to generate stress, which develops near liquid surface in a nuclear reactor wall and to contribute to further...
6553090 Control system of nuclear power plant, and control method thereof  
A method of controlling a nuclear power plant includes determining a first maximum linear heat generation rate and a first minimum critical power ratio by a core monitoring system, and determining...
6487266 Siphon water rods  
A fuel bundle assembly for a boiling water nuclear reactor comprising a plurality of fuel rods having respective fuel columns therein, and arranged in an ordered array, extending between upper and...
6216728 Tunable anticipatory output response valve control  
A valve control apparatus for generating an anticipatory output response for controlling a fluid flow in a fluid flow line includes a valve provided inside the fluid flow line, at least one sensor...
6198786 Methods of reactor system pressure control by reactor core power modulation  
A method of controlling the system pressure in a power generating system, having a turbine-generator and a BWR, that modulates the core thermal power of the reactor while maintaining the main...
6021169 Feedwater control over full power range for pressurized water reactor steam generators  
A feedwater control system and method for a pressurized water reactor steam generating system having first and second output signals. The first output signal is determined by first and second input...
5960049 Pump selection logic  
The operator of a nuclear steam supply system manually selects a lineup of either one, two, or three main feedwater pumps for normal reactor operation to generate power. This selection sets or...
5896434 Power supply system for driving reactor coolant recirculation pumps  
A power supply system for driving reactor coolant recirculation pumps within an advanced boiling water reactor is configured in such a manner that: at least one normal-operation busbar branches off...
5857006 Chimney for enhancing flow of coolant water in natural circulation boiling water reactor  
A chimney which can be reconfigured or removed during refueling to allow vertical removal of the fuel assemblies. The chimney is designed to be collapsed or dismantled. Collapse or dismantlement of...
5774517 Regulation of the core coolant flow rate of a natural circulation reactor  
A natural circulation reactor, especially a boiling water reactor, includes a reactor pressure vessel, a reactor core and a core jacket disposed within the reactor pressure vessel, surrounding the...
5610957 Reactor core coolant flow rate control system for a BWR type nuclear power plant  
A reactor core coolant flow rate control system for a BWR type nuclear power plant in which electric power is generated by a turbine-driven generator driven by a steam turbine rotating under the...
5579355 Heat dissipation system for a nuclear reactor, in particular a pressurized water reactor  
A nuclear reactor, in particular a pressurized water reactor, has a containment, a containment shell surrounding the containment and a concrete construction of a reactor building surrounding the...
5568527 Method and apparatus for remote ultrasonic inspection of core spray T-box welds  
A method and an apparatus for in situ ultrasonic inspection of the core spray T-box to thermal sleeve attachment weld and the core spray T-box to cover plate attachment weld in BWRs. The apparatus...
5528641 Fuel assembly  
A fuel assembly is provided with a coolant ascending path for making coolant rise and a water rod having a coolant descending path for conducting the coolant. A ratio of a flow area in a coolant...
5524128 Boiling water reactor stability control  
A control system for avoiding coupled neutronic-thermal hydraulic instabilities during maneuvering of a boiling water nuclear reactor that determines the average elevation in the reactor core of...
5519739 Boiling water type thermal neutron reactor and its operating method  
The reactor shut-down margin and the thermal margin, as well as the output per unit volume of the core is increased. When A is the total cross sectional area of the non-boiling water areas in the...
5444747 Jet pump electro-nozzle  
A method and a device for minimizing electrostatically enhanced deposition of charged particulates in the jet pump nozzles of operating BWR plants. The jet pump nozzle has an inner conducting...
5428651 Nuclear reactor locking piston drive system and valve assembly  
A locking piston drive system and valve assembly is provided for shutdown of a nuclear reactor. "Chatter" in a check valve assembly which occurs during charging and/or re-charging of control fluid...
5386440 Boiling water reactor  
An object of the present invention is to provide a boiling water reactor wherein two phase flow instability in a fuel assembly occurs scarcely. A bottom flow path is formed beneath a partition...
5323430 Method and system for fine control of thermal power of a boiling water reactor with natural circulation  
A method and a system for fine control of the thermal power of a nuclear boiling water reactor (BWR) with natural circulation. The reactor vessel, in which the core of such a reactor is enclosed,...
5293411 Nuclear reactor power control method and device  
Decreasing the speed of a pump supplying cooling water to the core in the boiling water type nuclear reactor based on a trip signal that is generated when a pump supplying feed water is tripped....
5280506 Steam isolation valve  
A main steam isolation valve of a reactor power plant comprises a valve body provided with inlet and outlet portions through which a steam flows, a cylindrical valve disk accommodated in the valve...
5268939 Control system and method for a nuclear reactor  
A nuclear reactor is joined to a steam turbine by a main steamline for discharging steam thereto. A plurality of flow control valves regulate flow to the turbine, and a bypass valve selectively...
5237595 Guide plate for guide tubes used in nuclear reactors  
An improved guide plate of the type used in the guide tubes of a nuclear reactor and having a central orifice for conducting coolant, and circular guide holes interconnected by slots for guidingly...
5213755 Low pressure coolant injection modification for boiling water reactors  
A conventional low pressure coolant injection system for boiling water reactors is provided. With the modification, the cross tie conduits and associated valves remain open between two LPCI...
5198185 Nuclear reactor flow control method and apparatus  
Method and apparatus for improving coolant flow in a nuclear reactor during accident as well as nominal conditions. The reactor has a plurality of fuel elements in sleeves and a plenum above the...
5192496 Fuel assembly and upper tie plate thereof  
The fuel assembly has fuel arrangement of a square lattice of 10 lines by 10 rows. Four water rods having a large diameter are arranged in central region of horizontal cross section wherein...
5180546 Boiling water reactor with downcomer steam release channel  
A natural circulation boiling water reactor system using free-surface steam separation incorporates a series of tubes near the inner wall of its reaction vessel extending from a downcomer to...
5164150 Method and apparatus for reducing parasitic bypass flow in a boiling water reactor  
A method and apparatus for improving the operating efficiency of a boiling water reactor is disclosed. Instead of coolant water being injected simultaneously at the bottom of the fuel rod...
5154880 Nuclear fuel bundle with coolant bypass channel  
A fuel bundle for a natural-circulation boiling-water reactor includes at least one coolant bypass tube which is at least partially open at both its top and bottom and extends about 2/3 of the...
5124114 Movement detection system  
In a system for detecting abnormal movement of a part of a gas-cooled nuclear reactor, for example abnormal tilting of a boiler unit caused by failure of a boiler support, a tracer material is...
5120493 Forced-circulation reactor with enhanced natural circulation  
A forced-circulation boiling-water reactor includes bypass check valves between a downcomer and a core inlet plenum. When the recirculation pumps are operating at full capacity, there is a maximum...
5118461 Flow rate measuring apparatus  
In an apparatus including a fluid circulation unit for allowing a fluid in a container to be circulated along a passage in the container, a flow rate measuring apparatus includes a rotational speed...
5100609 Enhancing load-following and/or spectral shift capability in single-sparger natural circulation boiling water reactors  
The present invention discloses an improved methodology for achieving the desirable feature of recirculation flow control in a sparger-type natural-circulation BWR, enabling reactors utilzing the...
5078953 Natural circulation boiling-water reactor with output power regulation  
A natural circulation boiling-water reactor system using free-surface steam separation incorporates a steam separator near the inner wall of its reaction vessel and extending into a downcomer....
5061435 High-temperature reactor  
High temperature reactor with residual-heat transfer system comprises a cooling gas intake at the bottom and cooling gas outlet at the top so that a cooling gas can flow from the bottom to the top...
5045272 Fluid temperature balancing system  
A steam generating system including a heat energy source, a feedwater heating section including at least one heat exchange unit (2) having a feedwater inlet, a device (10) for supplying feedwater...
5023047 Nuclear reactor having an ascending cooling path much greater than the descending cooling path  
A fuel assembly has a water rod which consists of a coolant ascending path and a coolant descending path, the coolant ascending path opening below a fuel support of a lower tie plate, the coolant...
4975239 BWR core flow measurement enhancements  
An apparatus and process for the accurate measurement and calibration of core flow in a boiling water reactor is disclosed. The reactor includes a pressure vessel having internal forced circulation...
4948551 Method of protecting a pressurized water nuclear reactor against failures in its emergency stop means  
In the event of an incident in the secondary cooling circuit of a nuclear reactor preventing cooling the water in the primary circuit of the steam generators (2) which are common to both circuits,...
4947485 Method for obtaining load-following capability in natural circulation, free-surface separation boiling water reactors  
The present invention is directed to a natural-circulation boiling water reactor of the free-surface separation type wherein housed within the reactor pressure vessel (RPV) is a nuclear core which...
Matches 1 - 50 out of 147 1 2 3 >