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8724768 |
System and method for storing energy in a nuclear power plant
A method of storing heat includes moving a portion of a heated fluid from at least one reactor core to at least one tank having solid media, storing heat from the portion of the heated fluid in... |
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8548114 |
Method and apparatus for repairing a jet pump line support
A jet pump sensing line support clamp may be used for sensing line repair, replacement, and damage prevention or reduction. The clamp may affix to jet pump sensing line supports and confine the... |
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8537961 |
Hybrid integrated energy production process
Disclosed is an advanced process that relates to the enhanced production of energy using the integration of multiple thermal cycles (Brayton and Rankine) that employ multiple fuels, multiple... |
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8064566 |
Electricity and steam generation from a helium-cooled nuclear reactor
Disclosed herein is a method comprising heating helium in a core of a nuclear reactor; extracting heat from the helium; superheating water to steam using the heat extracted from the helium,... |
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7436922 |
Electricity and steam generation from a helium-cooled nuclear reactor
Disclosed herein is a method comprising heating helium in a core of a nuclear reactor; extracting heat from the helium; superheating water to steam using the heat extracted from the helium;... |
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6977983 |
Nuclear power plant and a method of conditioning its power generation circuit
In a nuclear power plant making use of a high temperature gas cooled reactor, it is necessary, prior to commencing power generation and connection of a generator to an electrical distribution... |
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6795518 |
Integral PWR with diverse emergency cooling and method of operating same
Passive emergency cooling in response to a loss of coolant accident (LOCA) in a PWR, having an integral reactor pressure vessel incorporating the steam generators and housed in a small high... |
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6674830 |
Nuclear reactor plant
The subject of the present invention is to provide a nuclear reactor plant of which is a direct cycle nuclear reactor using a carbon dioxide as a coolant such that a heat evacuation for liquefying... |
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5335252 |
Steam generator system for gas cooled reactor and the like
A steam generator which finds particular application as a superheater and reheater for transfer of heat from the gas coolant of a nuclear power reactor to a secondary fluid medium. The lower... |
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5309492 |
Control for a closed cycle gas turbine system
A throttle valve having defined characteristics controls flow of gas from a gas heater to a turbine in a closed cycle gas turbine system. The gas heater may be a nuclear reactor fueled by fission... |
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5267288 |
Power station installation
In a power station installation which is designed as a combined installation, i.e. consists of a gas turbine group (2, 3, 4, 5, 6, 8) and of a steam cycle (13, 16, 17, 18, 19, 20) downstream of... |
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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... |
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5114667 |
High temperature reactor having an improved fluid coolant circulation system
A high temperature reactor has a downflow type nuclear reactor provided at the top portion thereof with a gas inlet and a plurality of steam generators provided around the nuclear reactor. The... |
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5087412 |
Nuclear reactor
A nuclear reactor using gas as a primary coolant and a liquid as a moderator and/or reflector. Gas coolant flows through inlet passages around the outlet plenum to a distributor plate. The gas is... |
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5037601 |
Glass-pool, gas-cycle nuclear power plant
A nuclear power plant that is of a walk-away type with an encapsulated reaction core in a glass matrix pool having a reactive Thorium/U233 composition in a containment structure that radiates... |
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4976914 |
Device for removing a blower from a gas-cooled nuclear reactor
In methods and devices for removing a blower from a gas-cooled nuclear reactor, removal bells have previously been used which require considerable free space above the blower in the case of... |
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4756873 |
Single loop nuclear power plant for current generation with a helium cooled high temperature reactor
A single loop nuclear power plant with a helium cooled high temperature reactor for generation of electric current, designed for a capacity of 1-5 MWe. The plant, which in addition to the high... |
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4725400 |
Nuclear reactor plant housed in a steel pressure vessel, with a gas cooled, small high temperature reactor
A nuclear reactor plant housed in a steel pressure vessel with a small high temperature reactor, together with a steam generator arranged over said reactor and with at least two circulating... |
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4713213 |
Nuclear reactor plant housed in a steel pressure vessel with a gas cooled small high temperature reactor
A nuclear reactor plant housed in a steel pressure vessel comprises a small high temperature reactor and a He/He heat exchanger located above the reactor, preferably followed by two circulating... |
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4694893 |
Unit for guiding the flow of cold gas in steam generators of high-temperature reactors
A unit for guiding the flow of cold gas from the annular chamber that is disposed between the pressure tank wall and the steam generator wall to the circulation fan of a steam generator of a... |
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4694897 |
Heat exchanger for heat exchange between hot gas and medium flowing through tube bundles
A heat exchanger for heat exchange between a hot gas and a flowing medium that is conveyed in tube bundle heat transfer surfaces, especially a steam generator. The heat exchanger includes a... |
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4692301 |
Steam generator heated with the cooling gas of a nuclear reactor
The invention concerns a steam generator heated by the cooling gas of a nuclear reactor and arranged in the reactor pressure vessel within a vertical shaft. A blower associated with the steam... |
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4689194 |
Nuclear reactor plant with a small high temperature reactor operating with spherical fuel elements
A nuclear reactor plant with a small high temperature reactor, principal heat exchangers located above the small high temperature reactor and housed in a steel pressure vessel, and a plurality of... |
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4683111 |
Gas circulator for a nuclear reactor and a method for use thereof
An improved gas circulator for a gas-cooled nuclear reactor system is disclosed which includes a stator, a rotor having a rotor shaft, and an impeller attached to one end thereof. A radial active... |
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4664871 |
Nuclear power installation with a high temperature pebble bed reactor
Disclosed is a nuclear power plant comprising a high-temperature pebble bed reactor contained in a cylindrical steel pressure vessel in which an upper part of the cylindrical steel pressure... |
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4585053 |
Heat exchanger for reactor core and the like
A compact bayonet tube type heat exchanger which finds particular application as an auxiliary heat exchanger for transfer of heat from a reactor gas coolant to a secondary fluid medium. The heat... |
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4576783 |
Heat pump augmentation of nuclear process heat
A system for increasing the temperature of a fluid heated by a high temperature gas cooled nuclear reactor to a sufficient temperature to supply the heat of reaction for a high temperature... |
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4571323 |
Cooling device
Device for the post-accident cooling of the confinement enclosure of a pressurized water nuclear reactor, wherein it comprises in series a turbine supplied by the hot, humid air contained in the... |
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4504439 |
Gas cooled nuclear reactor
It is desirable to being able to vary the temperature of a loop exposed to a flow of hot gases in gas cooled nuclear reactor installations without thereby affecting the gas temperature in the... |
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4466249 |
Gas turbine system for generating high-temperature process heat
The present invention relates to gas turbine systems for generating high-temperature process heat. To simplify the primary circuit and to eliminate the necessity of using the same circulation... |
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4413348 |
System for producing process heat
A system for producing process heat which employs a high temperature gas cooled nuclear reactor and is adapted to provide process heat at temperatures higher than the reactor core temperature. The... |
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4360496 |
Cooling system for auxiliary systems of a nuclear installation
Cooling system for auxiliary systems of a nuclear installation for heat removal from heat exchangers, the heat exchangers being connected on the primary side thereof to lines which may contain... |
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4357209 |
Nuclear divisional reactor
A nuclear divisional reactor including a reactor core having side and top walls, a heat exchanger substantially surrounding the core, the heat exchanger including a plurality of separate fluid... |
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4343681 |
Core energy plant with closed working gas circuit
A core energy plant with closed working gas circuit, in which within an or safety container there are arranged a reactor core of pre-stressed concrete for heating the working gas, a working gas... |
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4299660 |
Heat-extraction system for gas-cooled nuclear reactor
The cavity within a pressure vessel for a gas-cooled nuclear reactor is divided into chambers by an intermediate support floor, with the reactor core thereabove and heat-exchangers therebelow.... |
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4293384 |
Nuclear reactor plant for generating process heat
The invention is directed to a nuclear reactor plant having a primary medium circuit including a nuclear reactor for generating a flow of heated primary working medium and a heat exchanger having... |
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RE30630 |
Power plant secondary coolant circuit
In one embodiment, a closed cycle gas turbine system employs a precooler for cooling the gas prior to compression. A closed loop coolant circuit for the precooler includes a primary heat... |
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4258781 |
Suspension for a thermally heavy load cylindrical pipe assembly
A suspension for a thermally heavy load cylindrical pipe assembly of relatively large diameter, according to which the suspension includes a plate with chambers therein. This plate is at its... |
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4257846 |
Bi-brayton power generation with a gas-cooled nuclear reactor
Method and apparatus for generating power from a high temperature gas-cooled nuclear reactor utilizing two Brayton-type thermal cycle circuits exchanging heat through a common heat exchanger. The... |
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4229257 |
Method of operating a nuclear power installation and a power plant adapted for such operation
A primary working gas is heated in a high-temperature nuclear reactor and ives at least one primary turbine set to operate an electrical generator to generate electric power. Heat is abstracted... |
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4224983 |
Heat exchange apparatus for a reactor
A heat exchange apparatus for transferring heat from a reactor gas coolant to a secondary fluid medium. The heat exchange apparatus comprises an elongated vertically extending hole in a concrete... |
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4220200 |
Heat exchanger system
The heat exchanger system is used for gas-cooled high-temperature reactors. The high-temperature primary gas passes over a nest of blind tubes and thereafter flows over the tubes of a plurality of... |
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4212351 |
Articulated module flow guide system
A system is disclosed for promoting selective shell-side flow distribution between and providing structural support for modular straight tube bundles in a heat exchanger or the like, wherein a... |
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4193266 |
Gas turbine power plant
A gas turbine power plant has a gas turbine including both high-pressure and low-pressure turbine sections and a compressor including both high-pressure and low-pressure compressor sections. One... |
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4190493 |
Coated structural component for a high temperature nuclear reactor
A protective layer of tungsten or molybdenum is tightly adhered via an intermediate layer of pure nickel to a substratum of nickel-base alloy containing a carbide-former. The protected substratum... |
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4182413 |
Radial flow heat exchanger
An annular heat exchanger assembly is described which is particularly suited for structurally self supporting installation in a vapor generator associated with a nuclear reactor. The assembly... |
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4156659 |
Method of manufacturing a reducing gas useful in a direct reduction process
A method of reforming a fluid to make it suitable for use as a reducing gas in a direct reduction process is provided. The method is also taught in conjunction with a specific process for which it... |
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4144723 |
Power plant secondary coolant circuit
In one embodiment, a closed cycle gas turbine system employs a precooler for cooling the gas prior to compression. A closed loop coolant circuit for the precooler includes a primary heat... |
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4099554 |
Control system to regulate the wall temperature of a pressure vessel
A control system for a pressure vessel receiving a flow of hot rare gas, such as helium, from a nuclear reactor. The control system includes a thermocouple supported on the vessel wall within an... |
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4078899 |
Reaction vessel heated by helium
A reaction vessel for heating by helium under pressure comprising an upright container provided with an upper part and with a lower part constituting a heating space. In the lower container part... |