Matches 101 - 150 out of 222 < 1 2 3 4 5 >
Match Document Document Title
4793964 Small natural circulation pressurized water nuclear reactor  
A pressurized water nuclear reactor comprises a normally vertical main vessel externally duplicated by a confinement enclosure. The main vessel contains a simplified primary circuit essentially...
4788999 Automatic servo-controlled valve with high-speed opening  
The object of the invention is an automatic servo-controlled valve with high speed opening wherein the shutter is a hinged cover (20). Suitable locking means (30, 50) keep the cover (20) in a...
4783306 Method and device for passive transfer of heat from nuclear reactors to a public utility network, with automatic regulation of reactor power and automatic emergency shutdown and switchover to emergency cooling  
A pressurized water nuclear reactor has a reactor vessel arranged in a pool, which is filled with a neutron absorbing liquid, for example borated water. The reactor vessel is closed except for...
4777013 Nuclear reactor, in particular a high-temperature reactor  
A high-temperature gas cooled nuclear reactor system comprises a containment building, a concrete reactor pressure vessel inside the containment building, and a safety relief valve connected to the...
4756872 Nuclear power station for a gas-cooled high temperature pebble bed reactor  
The invention relates to a nuclear power station for a gas cooled high temperature pebble bed nuclear reactor. The nuclear power station is characterized by a combination of features, whereby the...
4753771 Passive safety system for a pressurized water nuclear reactor  
A passive safety system for a nuclear reactor is comprised of a first subsystem for circulating water solely by natural convection from a first branch to a second branch of a reactor coolant...
4728486 Pressurized water nuclear reactor pressure control system and method of operating same  
A pressure control system for a pressurized water nuclear reactor and method for quickly closing the valves associated with the pressurizer thereof has a temperature detection device on the loop...
4717532 Pressure control system for a pressurized water nuclear reactor plant  
An improved pressure control system for a pressurized water nuclear reactor plant contains a novel, two stage sparger in the pressurizer relief tank. The two stage sparger has a primary conduit and...
4702879 Nuclear reactor with passive safety system  
A pressurized nuclear water reactor has a substantially cylindrical flow liner with a cylindrical wall section and bottom and an open top. A barrel forms a riser chamber that contains the core in...
4692297 Control of nuclear reactor power plant on occurrence of rupture in coolant tubes  
The overflow in the secondary of a steam generator of a nuclear-reactor plant, which occurs when one or more primary tubes conducting the coolant are ruptured, is controlled. The secondary of the...
4687626 Passive safety device for emergency steam dump and heat removal for steam generators in nuclear power reactors  
The present invention provides a passive safety device for dumping steam from the steam generator of a nuclear power reactor in case of emergencies. The device comprises a steam ejector immersed in...
4672213 Container, especially for radioactive substances  
Container, especially for radioactive substances such as radioactive liquids, with an inner container for receiving these substances and an outer container, in which the inner container and thermal...
4664877 Passive depressurization system  
A passive depressurization system for use during cold shutdown of a pressurized water reactor receives saturated steam from the reactor's pressurizer, condenses the steam to water, and returns the...
4661312 Pressure relief system in nuclear reactors  
A nuclear reactor, particularly a light water reactor or a helium-cooled high-temperature reactor, is provided with a pressure relief system for relieving pressure resulting under fault conditions...
4654191 Pressure release arrangement for the safety containment of a pressurized water nuclear reactor  
A pressure release arrangement for a pressure container such as a safety containment of a nuclear reactor, wherein a pressure release pipe extends through the containment walls and is closed at its...
4645641 Process and installation to secure a prestressed concrete pressure vessel surrounded by a reactor protection building against excessive pressure and to prevent the release of activity to the environment  
A process and an installation for the securing against excessive pressure in a prestressed concrete pressure vessel of a gas cooled high temperature reactor and for the prevention of activity...
4629601 Stirrup-type support structure for nuclear power plant pressurizer valves  
A support structure for supporting a pressurizer safety and relief valve system above a pressurizer vessel comprises a ring girder which surrounds the pressurizer vessel wall and is supported on...
4620566 Device for protecting a container containing a pressurized fluid  
The invention relates to a device for protecting a container containing a pressurized fluid. The device comprises a protection valve and an isolating valve, connected in series and whose opening is...
4613253 Underwater discharge system  
An underwater discharge system for discharging an effluent overboard through an aperture in a wall of an at least partially submersed structure. The effluent is discharged through a conduit into a...
4610840 Fission product scrubbing system for a nuclear reactor  
A fission product scrubbing system comprises a water tank in the containment building; a dividing wall extending into the water tank for separating it into first and second compartments; a...
4601873 Method of avoiding or inhibiting intermixing of the atmosphere which exists in an enclosed space with a gaseous substance present in the same space  
In a method of inhibiting or avoiding intermixing of the atmosphere which exists in a closed nuclear reactor containment space with a gaseous substance present in the same space a change in density...
4595555 Power plants  
In a nuclear power plant, a reactor building and a building annex to this reactor building are constructed as a unitary reactor combination building in which a condensate storage tank is...
4589375 Steam generator for a liquid metal-cooled reactor  
A steam generator for transferring the heat carried by a liquid metal to a water - steam circuit. It comprises a drainage tank directly suspended at the lower end of the envelope. A drainage tube...
4584164 Valve control for low temperature overpressure protection in a nuclear power plant  
A control system for overpressure protection of the reactor coolant boundary (14) in a nuclear power plant, comprising a pressure relief line (18a) having a power operated relief valve (24a)...
4567016 Venting means for nuclear reactors  
The present invention is related to nuclear reactors. More specifically, this invention is directed to a means for venting pressurized water reactors.
4562036 Shock wave absorber having apertured plate  
The shock or energy absorber disclosed herein utilizes an apertured plate maintained under the normal level of liquid flowing in a piping system and disposed between the normal liquid flow path and...
4526743 Containment vessel for a nuclear reactor  
A containment vessel for a nuclear reactor having a dry well for mounting therein a pressure vessel for containing the nuclear reactor, a pressure suppressing chamber having a pool of coolant...
4515109 Apparatus for the production of steam by heat exchange between a heat-transfer liquid metal and feed water, comprising several liquid metal/inert gas interfaces  
Apparatus for the production of steam by heat-exchange between a heat-transfer liquid metal and feed-water, comprising an envelope (1) containing a tube bundle (8) which occupies only part of the...
4510118 Device for safety injection on a pressurized-water nuclear reactor  
Device for safety injection on a pressurized-water nuclear reactor, including at least two separate injection trains each consisting of at least one set of means (60, 61, 62) for pumping water from...
4505875 Coolant standpipe system for protection of a nuclear reactors safety vessel against breakdown from overpressure  
A standpipe runs up from a liquid storage vessel located between the safety vessel of a nuclear reactor and the safety enclosure around it and connected by a pressure equalization line to the...
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 other...
4500487 Pressure surge attenuator  
A pressure surge attenuation system for pipes having a fluted region opposite crushable metal foam. As adapted for nuclear reactor vessels and heads, crushable metal foam is disposed to attenuate...
4495147 Heat-retarding closure system for pressure relief openings of partitions, in nuclear reactor buildings  
Heat retarding closure system for partitions having pressure relief openings formed therein especially in nuclear reactor buildings where main coolant nozzles of a reactor pressure vessel penetrate...
4473528 Passive containment system  
The invention pertains to a containment system for a nuclear power plant which provides protection in the event of a loss of coolant accident or other malfunctions wherein the stored energy within...
4470948 Suppression of malfunction under water-solid conditions  
Malfunction under water-solid conditions responsive either to increase in mass flow or increase in heat flow into the reactor coolant is suppressed. The power-actuable reactor-coolant relief valve...
4457889 Process and device for emergency cooling of a nuclear reactor  
Process and device for emergency cooling of a nuclear reactor comprising a steam generator (2) heated by a primary circuit and cooled by a secondary circuit producing steam, and in which in case of...
4446081 Steam condensing apparatus  
In a steam condensing apparatus according to this invention, a plurality of branch pipes each having an exhaust nozzle are attached to the distal end of a guide pipe which extends into coolant to...
4428904 Blow-off device for limiting excess pressure in nuclear power plants, especially of the boiling water reactor-type  
In a blow-off device for limiting excess pressure in nuclear power plants, at least one condensation tube disposed so that a lower outlet end thereof is immersed in a volume of cooling water in a...
4426350 Valve support arrangement for pressurizer in a nuclear power plant  
A modularly constructable support arrangement is provided for pressurizer safety and relief valves in a nuclear power plant. A common header is supported by four sets of columnar legs which are...
4399082 Blowdown device for steam power plants  
Blowdown device for steam power plants includes a tube extending into a volume of water, the tube being formed with a multiplicity of holes having a substantially uniform diameter for introducing,...
4395380 Method of testing fluid flow condition in extension of a pipe  
A method for the remote testing of spray nozzles on headers in a nuclear reactor containment building to determine whether the nozzles are open or blocked. Heated air under pressure is supplied to...
4389368 Failsafe coolant pump for nuclear reactor  
An improved pressurized fluid reactor system having a fluid cooled reactor core in which the coolant pump for delivering fluid to the reactor core is driven by a pump motor through a unidirectional...
4388273 Apparatus for preventing the diversion of plutonium in nuclear fuel reprocessing  
Apparatus for preventing the diversion of plutonium in nuclear fuel reprocessing plants. The apparatus includes various piping arrangements which prevent plutonium in a liquid state from being...
4382907 Liquid metal cooled nuclear reactor  
The nuclear boiler comprises at least one heat exchanger located externally of the reactor vessel in order to effect heat exchange between the liquid metal coolant in the form of liquid and water...
4376091 Mechanical strainer unit  
The mechanical strainer unit is connected to a flanged conduit which originates in and extends out of a suppression chamber in a nuclear reactor. The strainer includes a plurality of centrally...
4363780 Boiling reactor  
Boiling reactor comprising a reactor core (1) and a pressure vessel (2) enclosing said reactor core and being provided with at least one conduit for discharged steam and at least one conduit for...
4362693 System for mitigating consequences of loss of coolant accident at nuclear power station  
The system according to the invention comprises a first room which accommodates a reactor plant and an active-type sprinkler means to condense steam released by the ebullient coolant after an...
4305896 Vent exit device for condensing steam  
A device having a tubular body of an increased diameter closed at its bottom and connected at its top to the lower end of a vent pipe in such a state that the tubular body is immersed in a water...
4297167 Nuclear reactor installation  
Nuclear reactor installation having a concrete cell disposed beneath the earth of a hill for enclosing activity-carrying components includes at least one additional concrete cell disposed in the...
4293385 Secondary coolant circuit for nuclear-reactors  
A secondary coolant circuit for a nuclear-reactor of the liquid-metal cooled type, said circuit comprising at least one intermediate exchanger mounted in the vessel of said reactor, outside said...
Matches 101 - 150 out of 222 < 1 2 3 4 5 >