Class 376/207 - WITH CONTROL OF REACTOR (E.G., CONTROL OF COOLANT FLOW)

Subclass of Class 376 - Induced nuclear reactions: processes, systems, and elements
Definition: Subject matter for changing (including "shut down")
No. of patents: 32
Last issue date: 02/19/2008

Number	Title	Issue Date
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
7257185	Fuel assembly and thimble screw of the same A fuel assembly includes a bottom nozzle set on a lower core plate of a nuclear reactor, a top nozzle with a hold down spring to urge the bottom nozzle against the lower core plate, guide thimbles which guide control rods, having passed through the top nozzle, towar...	08/14/2007
7222061	Method and arrangement for developing rod patterns in nuclear reactors In the method, a set of limits applicable to a test rod pattern design are defined, and a sequence strategy for positioning one or more subsets of the test rod pattern design is established. Reactor operation on a subset of the test rod pattern design, which may be ...	05/22/2007
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 wall is disclosed which may comprise a core support coolant inlet; a co...	02/21/2006
6938584	Feedwater control system considering pressure drop of feedwater control valve in nuclear power plant and control method therefor A feedwater control system considering a pressure drop of feedwater control valve in a nuclear power plant and a control method therefor are provided. In the feedwater control system, a first detection unit includes: a flow error signal generator for generating a fl...	09/06/2005
6925138	Reactor core and method for operating nuclear reactor The present invention is to provide a reactor core that allows a nuclear plant to continuously operate for a long term period, for example 15 years or longer, without requiring any fuel exchange, reduces the duration and number of maintenance steps involved in regul...	08/02/2005
6882696	Control rod for boiling water reactor and method for manufacturing the same A tie rod having a cruciform cross section is provided with steps for fixing sheaths at tips of cruciform arms of the tie rod; the tips of each of sheaths are fitted onto the steps of the tie rod, each of the sheaths having a U-shaped cross section; and each of the ...	04/19/2005
6873671	Reactor manual control system In a boiling water reactor controlling each control rod hydraulically by driving a solenoid valve, the control system comprises an operation control means 41 having a duplicated data processing unit for generating sequence patterns based on the timing of the ...	03/29/2005
6862329	In-cycle shuffle According to the method, a reactor core is shut down during the operation cycle. One or more fuel bundles of the reactor core are then moved to new positions within the reactor core to increase a total energy, output of the reactor core as compared to continuing ope...	03/01/2005
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
6795801	Apparatus and method for analyzing anisotropic particle scattering in three-dimensional geometries The disclosed method, a technique for analyzing anisotropic particle scattering, includes the step of establishing a three-dimensional geometric representation of an object. A set of rays is then projected through the three-dimensional geometric representation to pr...	09/21/2004
6721383	Maximum extended load line limit analysis for a boiling water nuclear reactor A computerized method for expanding the operating domain of a boiling water nuclear reactor that permits safe operation of the reactor at core flows lower than normal operating parameters is provided. The operating domain is characterized by a map of the reactor the...	04/13/2004
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
6674831	Fuel assembly and thimble screw of the same A fuel assembly includes a bottom nozzle set on a lower core plate of a nuclear reactor, a top nozzle with a hold down spring to urge the bottom nozzle against the lower core plate, guide thimbles which guide control rods, having passed through the top no...	01/06/2004
6631176	Fuel assembly A fuel assembly for a pressurized water reactor having control rod guide thimbles (5) each having a dashpot (12) for protecting against flexural deformation which may impair insatiability of a control rod. The fuel assembly includes, a plurality of contro...	10/07/2003
6611572	Determination of operating limit minimum critical power ratio A method and system for thermal-dynamic modeling and performance evaluation of a nuclear Boiling Water Reactor (BWR) core design is presented. A data processing system is used to execute specific program routines that simultaneously simulate the thermal o...	08/26/2003
6246741	Fuel assembly A fuel assembly for a pressurized water reactor having control rod guide thimbles (5) each having a dashpot (12) for protecting against flexural deformation which may impair insertability of a control rod The fuel assembly includes, a plurality of control...	06/12/2001
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
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 through the reactor core. In order to assure reliable heat...	10/29/1991
4871508	Method for operation of a light water boiling reactor A core of a light water boiling reactor comprises a plurality of vertical fuel assemblies (10) and a plurality of control rods, each control rod comprising four vertical blades arranged in a cruciform. The control rods are arranged with each one of their ...	10/03/1989
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
4495140	Permanent deactivation of nuclear reactor A gas cooled nuclear reactor is permanently deactivated on occurrence of an emergency by pyrolytic deposition of boron or refractory or stable compounds of boron in the fluid channels of the fuel elements of the reactor. The boron is enriched in boron 10....	01/22/1985
4421716	Safety monitoring and reactor transient interpreter An apparatus which monitors a subset of control panel inputs in a nuclear reactor power plant, the subset being those indicators of plant status which are of a critical nature during an unusual event. A display (10) is provided for displaying primary info...	12/20/1983
4170516	Method of operating a nuclear reactor In raising the power of a nuclear reactor, before the linear heat generating rate of nuclear fuel elements arranged in the core of the nuclear reactor reaches 240 W/cm, the power rise of the reactor is suspended at least once and the reactor power is held...	10/09/1979
4166762	Control apparatus with frequency-dependent control elements and application of the control apparatus to regulating the steam pressure of boiling water reactors A control loop for regulating the magnitude of a variable quantity of an apparatus to a reference value, for example the steam pressure in the output line from a boiling water reactor, wherein the instantaneous magnitude of the steam pressure is compared ...	09/04/1979
4153506	Method of starting operation of a nuclear reactor A method of starting operation of a nuclear reactor which contains fresh fuel rods comprising increasing a fuel power P(Kw/ft) produced by the fresh fuel rods to an amount determined by the following inequality; where D is a diameter of a fuel pellet of the fr...	05/08/1979
4096030	Control system for a boiling-water nuclear power plant A control system for a nuclear power plant which comprises a boiling-water reactor and a steam line including a control valve therein connecting the steam outlet from the reactor to a steam turbine includes a first controller of the "I-action" type respon...	06/20/1978
4093514	Method of bringing nuclear power plant to fractional electrical load conditions A method of bringing a nuclear power plant to fractional electric load conditions, which power plant comprises at least two nuclear reactors, at least one nuclear reactor being a breeder and both reactors transferring heat to the turbine working substance...	06/06/1978
4088182	Temperature control system for a J-module heat exchanger The level of primary fluid is controlled to change the effective heat transfer area of a heat exchanger utilized in a liquid metal nuclear power plant to eliminate the need for liquid metal control valves to regulate the flow of primary fluid and the temp...	05/09/1978
4057466	Conditioning of nuclear reactor fuel A method of conditioning the fuel of a nuclear reactor core to minimize failure of the fuel cladding comprising increasing the fuel rod power to a desired maximum power level at a rate below a critical rate which would cause cladding damage. Such conditio...	11/08/1977
3998693	Thermal margin control A monitoring system for providing warning and/or trip signals indicative of the approach of the operating conditions of a nuclear steam supply system to a departure from nucleate boiling or coolant temperature saturation. The invention is characterized by...	12/21/1976
3930937	Steam relief valve control system for a nuclear reactor A turbine follow system and method for Pressurized Water Reactors utilizing load bypass and/or atmospheric dump valves to provide a substitute load upon load rejection by bypassing excess steam to a condenser and/or to the atmosphere. The system generates...	01/06/1976

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Class 376/207 - WITH CONTROL OF REACTOR (E.G., CONTROL OF COOLANT FLOW)