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| Number | Title | Issue Date |
| 8009788 | Monitoring method and monitoring program for boiling water reactor, and acoustic damping method for boiling water reactor A boiling water reactor includes a reactor pressure vessel; a steam pipe for transporting steam generated in the reactor pressure vessel out from a steam dome positioned at an upper part of the reactor pressure vessel; a high pressure turbine connected to the steam ... | 08/30/2011 |
| 7970094 | Nuclear power plant and operation method thereof A nuclear power plant and method of operation for augmenting a second reactor thermal power output in a second operation cycle to a level larger than a first reactor thermal power output in the previous operation cycle. The plant is equipped, for example, with a rea... | 06/28/2011 |
| 7333584 | Nuclear power plant and operation method thereof A nuclear power plant and method of operation for augmenting a second reactor thermal power output in a second operation cycle to a level larger than a first reactor thermal power output in the previous operation cycle. The plant is equipped, for example, with a rea... | 02/19/2008 |
| 7280946 | Method and arrangement for determining pin enrichments in fuel bundle of nuclear reactor A method and arrangement of determining pin enrichments for a fuel bundle of a nuclear reactor, where a plurality of input parameters and target conditions may be input and enrichment changes, to be made across the fuel bundle, may be calculated using response matri... | 10/09/2007 |
| 7139351 | Method of and control system for controlling a nuclear reactor outlet temperature The invention relates to a control system for controlling an average temperature of a coolant at a reactor core outlet. The control system method detects an average temperature of the coolant at the reactor core outlet, compares the actual average temperature of the... | 11/21/2006 |
| 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 plane parallel to steam outlet faces of steam dryers provided inside... | 12/27/2005 |
| 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 to handle the increased thermal power. The thermal power of the nucle... | 06/21/2005 |
| 6891912 | Fuel assemblies in a reactor core and method of designing and arranging same A reactor core (104) includes fuel assemblies (202) arranged in a loading pattern (1100) in response to corresponding power levels of the fuel assemblies (202). A crud deposition model (412) is used to predict crud deposition on th... | 05/10/2005 |
| 6853930 | System for aiding the preparation of operation and maintenance plans for a power generation installation In order to provide an operation and maintenance planning aiding system for a power generation installation which prepares an operation plan for a plurality of power generation units by making use of actual plant data and based on a total judgement including a varie... | 02/08/2005 |
| 6691065 | System foraiding the preparation of operation and maintenance plans for a power generation installation In order to provide an operation and maintenance planning aiding system for a power generation installation which prepares an operation plan for a plurality of power generation units by making use of actual plant data and based on a total judgement includ... | 02/10/2004 |
| 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 a second maximum linear heat generation rate and a second ... | 04/22/2003 |
| 6477218 | Control system of nuclear power plant, and control method thereof A control system, and a control method, of a nuclear power plant capable of easily executing automatic output regulation by an automatic power regulator system even when a lower-accuracy maximum linear heat generation rate and a lower-accuracy minimum cri... | 11/05/2002 |
| 6400786 | Process and device for monitoring at least one operating parameter of the core of a nuclear reactor During operation of the nuclear reactor, at specified time intervals, a neutron flux is measured using a set of neutron flux detectors which are fixed and arranged in the core (1) of the nuclear reactor, the maximum number n of detectors (8) being 15% of ... | 06/04/2002 |
| 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 turbine control valves in a constant steady position is describ... | 03/06/2001 |
| 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 signals, and, when combined with a third input signal aut... | 02/01/2000 |
| 5555279 | System for monitoring and controlling nuclear reactors A computer-based power oscillation detection system and method for detecting, monitoring and indicating thermal-hydraulic stability margin in a nuclear reactor is provided. A group of neutron flux detectors is distributed throughout the reactor core, in c... | 09/10/1996 |
| 5528639 | Enhanced transient overpower protection system An enhanced protection system for protecting against transient overpower in a boiling water nuclear reactor which automatically adjusts the reactor over-power protection trip setpoints to be a controlled margin above the operating power level, so that enh... | 06/18/1996 |
| 5473644 | Apparatus for measuring power of nuclear reactor and method for manufacturing the same An apparatus for measuring the power of a nuclear reactor having a sensor assembly disposed in a core section inside the nuclear reactor. The sensor assembly includes a cover tube made of metal and press-fitted on the outer surface of a rod-shaped core tu... | 12/05/1995 |
| 5406598 | System for monitoring power of nuclear reactor A system for monitoring power, particularly a power distribution, of a nuclear reactor includes a plurality of neutron flux measuring units disposed in a core of the nuclear reactor for measuring neutron flux in the core and generating neutron flux signal... | 04/11/1995 |
| 5317606 | Automation system for nuclear power plants This invention relates to an automation system for nuclear power plants. This system comprises operation plan making means, supervisory control means, and control means for controlling controlled objects. The operation plan making means makes a new operat... | 05/31/1994 |
| 5192493 | Median signal selector for feedwater control systems A system for improving the performance of nuclear power plant feedwater control systems and simplifying steam generator low water level reactor protection logic includes a plurality of water level channels for measuring steam generator water level and gen... | 03/09/1993 |
| 5169592 | Method of protecting a nuclear reactor in the event of a load increase An emergency stop of a pressurized water reactor to be protected is triggered when the nuclear power (ET) thereof reaches an emergency stop limit (LP). The value of this limit is lower with lower operating temperatures (ST) of the reactor.... | 12/08/1992 |
| 5120489 | Hydraulic control rod drive A drive for positioning a control rod in a nuclear reactor core is disclosed. The drive includes a housing having a piston disposed therein, with a piston rod extending from the piston and through the housing for being joinable to the control rod. A drivi... | 06/09/1992 |
| 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. Steam so collected supplements the main steam flow from the re... | 01/07/1992 |
| 5061431 | Method of determining the enthalpy and moisture content of wet steam A simple and accurate method for determining the enthalpy of wet steam using pressure and moisture content values. Moisture content is determined by measuring sonic velocity of the steam, which is dependent upon enthalpy. A small sample of the wet steam i... | 10/29/1991 |
| 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 with the RPV defines an annulus region which is in flow co... | 08/07/1990 |
| 4943408 | Method and apparatus for operating nuclear electric power generating plants In a nuclear electric power generating plant connected to an electric power system, an output of a nuclear reactor of the plant is reduced during a nighttime operation, increased to a predetermined level during a daytime operation and reduced during a lun... | 07/24/1990 |
| 4912732 | Automatic steam generator control at low power The steam generator water level, the feed water temperature, and the reactor power are continuously measured and a level signal (76), a temperature signal (78), and a power signal (80) commensurate with these measurements are respectively generated. From ... | 03/27/1990 |
| 4826647 | Spectral shift reactor A mechanical spectral shift reactor comprises apparatus for inserting and withdrawing water displacer elements having differing neutron absorbing capabilities for selectively changing the water-moderator volume in the core thereby changing the reactivity ... | 05/02/1989 |
| 4707324 | Controlling the response of a pressurized water reactor to rapid fluctuations in load The setpoints for control systems in a pressurized water reactor are adjusted by an amount corresponding to the expected change in the controlled process variable resulting from rapid fluctuations in load to reduce the duty time of the control system comp... | 11/17/1987 |
| 4694693 | Check valve test method using truncated accumulator blowdown A method for testing a normally closed check valve connected in series with an isolation valve at the outlet of a passive injection system includes adjusting pressure upstream and downstream of the check and isolation valves to an upstream pressure higher... | 09/22/1987 |
| 4650633 | Method and apparatus for protection of pump systems A control apparatus and method for restricting liquid flow in a liquid moving pump, usually of the centrifugal type, to prevent pump cavitation and pump prime mover overloading. The control apparatus includes sensors to detect liquid temperature and press... | 03/17/1987 |
| 4582669 | Xenon suppression in a nuclear fueled electric power generation system The fissile inventory required in operating a negative power coefficient nuclear reactor in an electric power generating system is reduced by cycling the load imposed on the system when 100% power can no longer be maintained at equilibrium due to xenon po... | 04/15/1986 |
| 4472345 | Load control system for nuclear power plant A load control system for a boiling water reactor power plant. A recirculating pump speed demand signal and a total steam flow demand signal are derived on the basis of combination of a first control signalproduced in accordance with a power difference si... | 09/18/1984 |
| 4424186 | Power generation Excessive swing of the feedwater in power supply apparatus on the occurrence of a transient is suppressed by injecting an anticipatory compensating signal into the control for the feedwater. Typical overshoot occurs on removal of a large part of the load,... | 01/03/1984 |
| 4278500 | Pressurized water reactor The primary coolant fluid is circulated within at least one primary loop between a steam generator and a pressure vessel. Within the steam generator, the primary fluid flows through a tube bundle and exchanges heat with a secondary fluid which is admitted... | 07/14/1981 |
| 4150546 | Method and apparatus for load following with a single-cycle boiling moderator-coolant nuclear reactor The invention is directed to a method and apparatus for providing a single-cycle boiling moderator-coolant nuclear reactor which accommodates changes in demand with a turbine generator on direct governor control. Current single-cycle boiling moderator-coo... | 04/24/1979 |
| 4104117 | Nuclear reactor power generation The feedwater of a nuclear reactor at low-power levels, particularly during start-up, is controlled by combining an error signal component dependent on the departure of the actual level in the steam generator from a preset level and a component dependent ... | 08/01/1978 |
| 4080251 | Apparatus and method for controlling a nuclear reactor A control system and method for a nuclear steam supply system for calculating the appropriate operating limits of the system based on the system's design limits. The control system monitors the appropriate parameters of the nuclear steam supply system, mo... | 03/21/1978 |
| 4079236 | Method and apparatus for monitoring the axial power distribution within the core of a nuclear reactor, exterior of the reactor A method and apparatus for establishing the axial flux distribution of a reactor core from monitored responses obtained exterior of the reactor. The monitored responses obtained exterior of the reactor. The monitored responses are obtained from at least t... | 03/14/1978 |
