| Class / Patent application number | Description | Number of patent applications / Date published |
|---|
| 376210000 | By coolant flow | 36 |
| 20080232534 | REFLECTOR CONTROL TYPE FAST REACTOR - A reflector control type fast reactor | 09-25-2008 |
| 20080273650 | FAST REACTOR HAVING REFLECTOR CONTROL SYSTEM AND NEUTRON REFLECTOR THEREOF - A fast reactor having a reflector control system is provided which decreases the change in reactivity of the reactor core with time without performing control of a reflector lifting speed and that of a water flow rate. The above fast reactor has a liquid metal coolant, a reactor core immersed therein, and a neutron reflector which is provided outside the reactor core and which is moved in a vertical direction for adjusting leakage of neutrons therefrom for controlling the reactivity of the reactor core. The neutron reflector described above is gradually moved in an upward direction with the change in reactivity caused by fuel burn-up, and at least a part of a lower region of the neutron reflector is a high reflection region having a high neutron reflection ability as compared to that of the other region. The high reflection region is located from the bottom to a place between one fourth and one half of the height of the neutron reflector from the bottom end thereof. | 11-06-2008 |
| 20080310575 | Nuclear Reactor, In Particular a Liquid-Metal-Cooled Nuclear Reactor - A nuclear reactor ( | 12-18-2008 |
| 20080317191 | OPERATING METHOD OF NUCLEAR REACTOR AND NUCLEAR POWER GENERATION PLANT - The present invention decreases the temperature of feed water supplied to the reactor of a set power when the flow rate of coolant supplied to the core of the reactor increases in the end of an operation cycle. This operating method can increase the thermal power of the nuclear power generation plant and increase the economical efficiency of fuel even when the operation cycle is prolonged. Particularly, even when the core flow rate increases in the end of the operation cycle, this method can suppress the rise of the cooling water temperature at the inlet of the core. Consequently, this invention can make the reactivity gain higher than that when the core flow rate is singly increased. | 12-25-2008 |
| 20090016479 | FEEDWATER TEMPERATURE CONTROL METHODS AND SYSTEMS - In various embodiments, a system for controlling the power level of a natural circulation boiling water nuclear reactor (NCBWR) is provided. In various embodiments, the system includes a heating subsystem for heating feedwater flowing into an annulus of a NCBWR to increase the temperature of recirculation water flowing through the core above a predetermined recirculation water operating temperature. Additionally the system includes a temperature sensor operable to sense the temperature of the feedwater flowing into the annulus. The temperature sensor is communicatively connected to a temperature controller operable to command the heating subsystem to increase the temperature of the feedwater flowing into the annulus to a requested temperature above a predetermined operating temperature of the feedwater flowing into the annulus. By increasing the temperature of the feedwater flowing into the annulus, the temperature of the recirculation water is increased above the predetermined recirculation water operating temperature causing a reduction in the power level generated by the NCBWR core. | 01-15-2009 |
| 20090141848 | NUCLEAR REACTOR PRIMARY CIRCUIT - The invention relates to a nuclear reactor primary circuit comprising a primary pipeline ( | 06-04-2009 |
| 20090154632 | Optimizer Hydraulic Enhancement Using Milled Plate - A radial flow reactor fluid duct distribution apparatus is presented. The apparatus includes a plate of sufficient thickness to impart strength to the fluid flow duct and is milled to have narrow slots allowing fluid to flow through the plate, while preventing the passage of catalyst through the plate. | 06-18-2009 |
| 20090175402 | Method and system for providing fuel in a nuclear reactor - Exemplary embodiments provide automated nuclear fission reactors and methods for their operation. Exemplary embodiments and aspects include, without limitation, re-use of nuclear fission fuel, alternate fuels and fuel geometries, modular fuel cores, fast fluid cooling, variable burn-up, programmable nuclear thermostats, fast flux irradiation, temperature-driven surface area/volume ratio neutron absorption, low coolant temperature cores, refueling, and the like. | 07-09-2009 |
| 20100111242 | METHOD FOR OPERATING A REACTOR OF A NUCLEAR PLANT - A method of operating a nuclear reactor is disclosed. The reactor ( | 05-06-2010 |
| 20100150293 | PROCESS FOR INCREASING THE EFFICIENCY OF HEAT REMOVAL FROM A FISCHER-TROPSCH SLURRY REACTOR - The present invention is directed to a cooling system for removing heat from a Fischer-Tropsch (F-T) slurry reactor. The cooling system including at least one downcomer having an upper portion, a lower portion, and a diameter; the at least one downcomer disposed within the F-T reactor to deliver a coolant downward through the F-T reactor at a predetermined velocity, the at least one downcomer extending a length within the F-T reactor wherein the coolant is introduced into the upper portion of the at least one downcomer in a substantially liquid phase; the diameter of the at least one downcomer and the pressure of the introduced coolant cooperate to increase the coolant velocity thereby generating backpressure in the at least one downcomer to maintain the coolant in the substantially liquid phase along the length of the at least one downcomer. The cooling system further including a plenum connected to the lower portion of the at least one downcomer; the plenum in fluid communication with the at least one downcomer wherein the coolant remains in the substantially liquid phase. Additionally, the cooling system includes at least one riser having a length and extending upward from the plenum; the at least one riser in fluid communication with the plenum wherein a portion of the coolant vaporizes to provide a boiling heat transfer surface on the at least one riser. | 06-17-2010 |
| 20100220829 | CONTROL ROD GUIDE TUBE AND METHOD FOR PROVIDING COOLANT TO A NUCLEAR REACTOR FUEL ASSEMBLY - Control rod guide tubes for a nuclear reactor having a body with an axial length that defines a lower end portion and an upper end portion and a cavity within a substantial length of the body. Orifices are included at the upper and lower end portions of the body. A control rod chamber is located within the cavity and is configured for receiving a control rod. A plurality of ports is coupled to the cavity and is positioned at a substantial length from the upper end portion of the body. Also included are at least two flow channels within the cavity that extend a substantial portion of the axial length of the body. Each flow channel is fluidly coupled to one or more of the ports for receiving fluid flow from outside the body and an outlet proximate to the upper end portion of the body for providing the received fluid flow. | 09-02-2010 |
| 20100232560 | PH ADJUSTING SYSTEM AND PH ADJUSTING METHOD - A pH adjusting system includes a water pit for refueling | 09-16-2010 |
| 20100266085 | Nuclear fission reactor, flow control assembly, methods therefor and a flow control assembly system - A nuclear fission reactor, flow control assembly, methods therefor and a flow control assembly system. The flow control assembly is coupled to a nuclear fission module capable of producing a traveling burn wave at a location relative to the nuclear fission module. The flow control assembly controls flow of a fluid in response to the location relative to the nuclear fission module. The flow control assembly comprises a flow regulator subassembly configured to be operated according to an operating parameter associated with the nuclear fission module. In addition, the flow regulator subassembly is reconfigurable according to a predetermined input to the flow regulator subassembly. Moreover, the flow control assembly comprises a carriage subassembly coupled to the flow regulator subassembly for adjusting the flow regulator subassembly to vary fluid flow into the nuclear fission module. | 10-21-2010 |
| 20100266086 | Nuclear fission reactor, flow control assembly, methods therefor and a flow control assembly system - A nuclear fission reactor, flow control assembly, methods therefor and a flow control assembly system. The flow control assembly is coupled to a nuclear fission module capable of producing a traveling burn wave at a location relative to the nuclear fission module. The flow control assembly controls flow of a fluid in response to the location relative to the nuclear fission module. The flow control assembly comprises a flow regulator subassembly configured to be operated according to an operating parameter associated with the nuclear fission module. In addition, the flow regulator subassembly is reconfigurable according to a predetermined input to the flow regulator subassembly. Moreover, the flow control assembly comprises a carriage subassembly coupled to the flow regulator subassembly for adjusting the flow regulator subassembly to vary fluid flow into the nuclear fission module. | 10-21-2010 |
| 20100266087 | Nuclear fission reactor, flow control assembly, methods therefor and a flow control assembly system - A nuclear fission reactor, flow control assembly, methods therefor and a flow control assembly system. The flow control assembly is coupled to a nuclear fission module capable of producing a traveling burn wave at a location relative to the nuclear fission module. The flow control assembly controls flow of a fluid in response to the location relative to the nuclear fission module. The flow control assembly comprises a flow regulator subassembly configured to be operated according to an operating parameter associated with the nuclear fission module. In addition, the flow regulator subassembly is reconfigurable according to a predetermined input to the flow regulator subassembly. Moreover, the flow control assembly comprises a carriage subassembly coupled to the flow regulator subassembly for adjusting the flow regulator subassembly to vary fluid flow into the nuclear fission module. | 10-21-2010 |
| 20100266088 | Nuclear fission reactor, flow control assembly, methods therefor and a flow control assembly system - A nuclear fission reactor, flow control assembly, methods therefor and a flow control assembly system. The flow control assembly is coupled to a nuclear fission module capable of producing a traveling burn wave at a location relative to the nuclear fission module. The flow control assembly controls flow of a fluid in response to the location relative to the nuclear fission module. The flow control assembly comprises a flow regulator subassembly configured to be operated according to an operating parameter associated with the nuclear fission module. In addition, the flow regulator subassembly is reconfigurable according to a predetermined input to the flow regulator subassembly. Moreover, the flow control assembly comprises a carriage subassembly coupled to the flow regulator subassembly for adjusting the flow regulator subassembly to vary fluid flow into the nuclear fission module. | 10-21-2010 |
| 20100322368 | Enhanced Steam Dump (Bypass) Control System - The present invention relates to a method of controlling a nuclear reactor during a transient period. The method includes actuating the steam dump system in response to a temperature error signal and a power mismatch signal. | 12-23-2010 |
| 20110026659 | Control loop for a power plant - A control loop includes a pressure vessel, a condenser and a piping provided between the pressure vessel and the condenser. The piping includes a steam pipe for transferring dry air from the pressure vessel into the condenser, a turbine bypass pipe for transferring wet air from the pressure vessel into the condenser; a water-feeding pipe for transferring a first amount of water from the condenser into the pressure vessel and a pump bypass pipe for transferring a second amount of water from the condenser into the pressure vessel. Turbines are provided on the steam pipe and driven by the dry air. A turbine-controlling valve is provided on the steam pipe and operable to control the flow rate of the dry air. A turbine bypass valve is provided on the turbine bypass pipe and operable to control the flow rate of the wet air. | 02-03-2011 |
| 20110158370 | Offshore energy carrier production plant - Disclosed is an offshore fixed, moored, or mobile energy carrier production plant. The plant's energy source for the energy intensive processes of producing an energy carrier is nuclear in nature and the resulting energy carriers of the plant range from hydrogen to hydrocarbons such as methanol and jet fuel. The offshore energy carrier production plant will be able to produce energy carriers at a reduced cost, increased sustainability and scalability, increased safety, and with fewer environmental and social impacts than heretofore possible. The resulting energy carrier products can then be transported by marine vessels, pipelines, and other transportation means or any combination of transportation means thereof to be distributed to end use energy carrier consuming devices and products such as fuel cell applications in a variety of industries as well as internal combustion engines. | 06-30-2011 |
| 20110164712 | Standing wave nuclear fission reactor and methods - Disclosed embodiments include nuclear fission reactor cores, nuclear fission reactors, methods of operating a nuclear fission reactor, and methods of managing excess reactivity in a nuclear fission reactor. | 07-07-2011 |
| 20120087455 | Electromagnetic flow regulator, system, and methods for regulating flow of an electrically conductive fluid - Disclosed embodiments include electromagnetic flow regulators for regulating flow of an electrically conductive fluid, systems for regulating flow of an electrically conductive fluid, methods of regulating flow of an electrically conductive fluid, nuclear fission reactors, systems for regulating flow of an electrically conductive reactor coolant, and methods of regulating flow of an electrically conductive reactor coolant in a nuclear fission reactor. | 04-12-2012 |
| 20120155594 | CONTROL SYSTEM AND METHOD FOR PRESSURIZED WATER REACTOR (PWR) AND PWR SYSTEMS INCLUDING SAME - A pressurized water reactor (PWR) comprises a pressure vessel, a reactor core disposed in the pressure vessel, an integral or external pressurizer, primary coolant disposed in the pressure vessel and heated by operation of the reactor core, and a steam generator disposed in the pressure vessel and configured to convert secondary coolant in the form of feedwater into steam by heat transfer from the primary coolant heated by operation of the reactor core to secondary coolant in the steam generator. A controller is configured to perform a PWR control method including the operations of (i) adjusting one or more parameters of the PWR and (ii) adjusting a pressurizer water level setpoint based on a predicted direction and magnitude of change of a pressurizer water level of the PWR predicted to result from the adjusting (i). | 06-21-2012 |
| 20120163524 | Tie Plate With Variable Orifice and Methods for Selective Control of Fuel Assembly Coolant Flow - In a nuclear reactor core, a lower tie plate assembly is provided with asymmetric features designed to control or vary a loss coefficient as a function of rotation of the associated fuel assembly. An associated method is provided to control the flow of coolant through the associated fuel assembly via rotation of the fuel assembly relative to the fuel support member. Control of the flow can be used to adjust assembly flow rate, assembly power and flow quality within the fuel assembly, among other assembly operational characteristics. Such flow control will impact the flow through other assemblies as well, since core flow remains generally fixed. On a core-wide basis, such flow control can be used to optimize core wide parameters. Optimization parameters of particular interest are the fuel cycle cost and moisture carryover. | 06-28-2012 |
| 20120170702 | SYSTEM OF CONTROLLING STEAM GENERATOR LEVEL DURING MAIN FEED-WATER CONTROL VALVE TRANSFER FOR NUCLEAR POWER PLANT - A system and a method of transforming a gain and an integral time constant of a proportional-integral (PI) controller according to a timer lapse time to relieve an excessive phenomenon of a steam generator level caused by rapid changes in open degrees of a downcomer feed-water valve and an economizer feed-water valve when reactor power transfers between low and high power sections. Accordingly, an excessive phenomenon of a steam generator level is relieved at a transfer time when reactor power transfers between low and high power sections. Therefore, a possibility of a stop of a reactor caused by the excessive phenomenon of the steam generator level is reduced to relieve burden on an operator and improve an operation rate and economic feasibility of a nuclear power plant. | 07-05-2012 |
| 20120207260 | Heat Removal System and Method for Use with a Nuclear Reactor - A nuclear reactor includes a reactor vessel, a containment vessel that surrounds the reactor vessel, and a condenser that receives coolant from within the reactor vessel. The containment vessel and the condenser are at least partially submerged within a common reactor pool of liquid. | 08-16-2012 |
| 20130136222 | CONTROL SYSTEM FOR PLANT - In a control system for a plant controlling a plant such as a nuclear power plant | 05-30-2013 |
| 20130301770 | System and Method for Annealing Nuclear Fission Reactor Materials - Illustrative embodiments provide systems, methods, apparatuses, and applications related to annealing nuclear fission reactor materials. | 11-14-2013 |
| 20140153685 | System and Method for Annealing Nuclear Fission Reactor Materials - Illustrative embodiments provide systems, methods, apparatuses, and applications related to annealing nuclear fission reactor materials. | 06-05-2014 |
| 20140205048 | Systems and Methods for Providing Override Control for a Feedwater Pump Recirculation Valve - Systems and methods for providing override control for a feedwater pump recirculation valve are provided. According to one embodiment, a system may include a controller and a processor communicatively coupled to the controller. The processor may be configured to receive one or more measurements associated with pump motor power driving feedwater pump flow. The feedwater pump recirculation valve may be configured to maintain a predetermined minimum recirculation flow through the feedwater pump by regulating recirculation pump flow through a recirculation line. The processor may be also configured to calculate, based at least in part on the one or more measurements, the recirculation pump flow, and compare the recirculation pump flow to the predetermined minimum recirculation flow. Based at least in part on the comparing, the processor may selectively provide an override control signal to the feedwater pump recirculation valve to selectively modify the recirculation pump flow. | 07-24-2014 |
| 20160180974 | PASSIVE INTEGRAL ISOLATION VALVE | 06-23-2016 |
| 20160189807 | STEAM GENERATOR LEVEL CONTROL SYSTEM AND METHOD OF PREVENTING OSCILLATION OF STEAM GENERATOR LEVEL - Provided are a method and system for improving control of a steam generator level for preventing oscillation of the steam generator level in a nuclear power plant. In order to prevent oscillation of a steam generator level and resultant shutdown of a nuclear reactor, which may be caused when a high-level priority control function is frequently and repeatedly turned on/off as the steam generator level is excessively increased, by improving a feedwater control system in the nuclear power plant, a proportional integral control value may be controlled to be reduced, and thus, output while a certain condition is met after a high-level priority mode is deactivated or a signal instructing to enter the high-level priority control mode may be controlled not to be output. | 06-30-2016 |
| 20160189808 | AUTOMATIC HYDROPNEUMATIC ACTUATION DEVICE - A control assembly for a nuclear reactor having a pump includes a duct having an inner volume and defining a coolant flow path, a plug fixed to the duct, a rod disposed within the inner volume and having a rod end that is configured to engage a neutron modifying material, a first piston disposed within the inner volume, slidably coupled to the duct, and coupled to the rod, and a biasing member coupled to the rod and the first piston. The biasing member is positioned to apply a biasing force that repositions the first piston, the rod, and the neutron modifying material in response to a loss of pump flow without scram condition. | 06-30-2016 |
| 376211000 | Exterior of core (e.g., secondary loop control) | 4 |
| 20090092216 | STEAM GENERATOR DUAL SYSTEM SLUDGE AND LOOSE PARTS COLLECTOR - A U-tube steam generator having a dual system for collecting loose parts and sludge. A loose parts collector having a water overflow edge is disposed between a feedwater inlet and a tube bundle of the steam generator. A sludge collector having a water outlet is disposed downstream of the overflow edge of the loose parts collector and maintains a pressure differential between a water inlet of the sludge collector and the water outlet. | 04-09-2009 |
| 20130108003 | AUXILIARY FEEDWATER VALVE CONTROL APPARATUS OF STEAM GENERATOR | 05-02-2013 |
| 20130216015 | INTEGRATED SODIUM-COOLED FAST NUCLEAR REACTOR - An improvement to an SFR reactor of the integrated type wherein each of the outlet windows of the intermediate exchangers is surrounded in an enclosure in fluid communication with a pipe shaped into a toroid; and each of the inlets of the pump group which pumps the sodium from the hot area to the cold area through the intermediate exchangers is also in fluid communication with the toroid, such that the primary sodium originating from the hot area and exiting from the intermediate exchangers flows through the toroid and is then directed to the cold area by the said pump group. | 08-22-2013 |
| 20150049850 | COMPACT NUCLEAR POWER GENERATION SYSTEM - [Problem] To build a secure and high-efficiency power generation system while achieving a further reduction in the size of the entire system. [Solution] A compact nuclear power generation system is provided with a reactor ( | 02-19-2015 |
