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| Number | Title | Issue Date |
| 7526057 | Decay heat removal system for liquid metal reactor A decay heat removal system for a liquid metal reactor in which a decay heat exchanger (DHX) is installed concentrically with an intermediate heat exchanger (IHX) in the same cylinder which separates the DHX and IHX from the reactor pool fluid, and serves to remove ... | 04/28/2009 |
| 7522693 | Passive safety-grade decay-heat removal method and decay-heat removal system for LMR with pool direct heat cooling process A direct pool cooling type passive safety grade decay heat removal method and system for removing core decay heat in a pool type liquid metal reactor when a normal heat removal system breaks down. In the liquid metal reactor comprising a reactor vessel, the interior... | 04/21/2009 |
| 7308070 | Stable and passive decay heat removal system for liquid metal reactor A decay heat removal system for a liquid metal reactor, in which a decay heat exchanger (DHX) is installed concentrically with an intermediate heat-exchanger (IHX) in the same cylinder which separates the DHX and IHX from the reactor pool fluid, and serves to remove... | 12/11/2007 |
| 7251939 | General method for disposal of produced water A method and apparatus useful for disposing of the high volumes of produced water associated with coal bed methane natural gas wells. The method taught is to create steam from the produced water and vent the steam into the atmosphere. The apparatus taught utilizes a... | 08/07/2007 |
| 7245688 | Cooling system This invention relates to a nuclear reactor plant which includes a nuclear heat source (12), and a cooling system (10). The cooling system (10) includes at least two cooling circuits (26), each of which includes a plurality of coolant cha... | 07/17/2007 |
| 7222058 | Method of modeling and sizing a heat exchanger A method of modeling a heat exchanger is disclosed and comprises assigning input temperatures, assumed output temperatures, and a set of flow rates, inputting the parameters into a set of equations arranged to calculate a heat transfer coefficient, inputting paramet... | 05/22/2007 |
| 7154982 | Compact pressurized water nuclear reactor A compact pressurised water nuclear reactor comprises a primary circuit fully integrated into the reactor vessel (10). Thus, a single steam generator (12) forms the cover of the vessel (10) and the pressuriser (30) and the primary pumps (... | 12/26/2006 |
| 7025807 | Method for absorbing vapors and gases from pressure vessels The invention relates to a process for absorbing vapors and gasses by controlling overpressure in storage tanks during filling, transport and storing of fluids in liquid form. The process includes leading of gas down to the bottom of the tank, where a major part of ... | 04/11/2006 |
| 6914955 | Heat exchanger tube support structure A support plate for retaining tube array spacing within a heat exchanger tube and shell structure. The support plate having a plurality of individual tube receiving apertures formed therein. Each aperture has at least three inwardly protruding members and bights are... | 07/05/2005 |
| 6912263 | Method and device for feeding at least one steam generator of a pressurized-water nuclear reactor during periods of reactor shutdown At least one injector condenser (20) is used to supply secondary feedwater to the steam generator (1) during a phase in the course of which the temperature and the pressure of the coolant of the reactor coolant system (2) of the nuclear reactor ... | 06/28/2005 |
| 6904754 | Steam generator for liquid metal reactor and heat transfer method thereof Disclosed herein is a steam generator for a liquid metal reactor and a heat transfer method thereof, and more particularly a steam generator for a liquid metal reactor having intermediate fluid forcibly circulated therein and structurally improved coiled heat transf... | 06/14/2005 |
| 6810099 | Boiling water reactor nuclear power plant and its construction method The present invention provides a boiling water reactor nuclear power plant in which a reactor core support plate, upper grid plate, and a reactor core consisting of fuel assemblies supported by these plates are provided in the inner base portion of a nuclear reactor... | 10/26/2004 |
| 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 pressure containment vessel, is provided by circulating cooling water throug... | 09/21/2004 |
| 6718001 | Nuclear reactor In an indirect cycle nuclear reactor, a size of the reactor containment vessel is decreased by removing decay heat inside the reactor pressure vessel without using any active component to improve the economic feasibility. A main steam pipe communicating with a heat ... | 04/06/2004 |
| 6618461 | Systems and methods to enhance passive containment cooling system A nuclear reactor containment cooling system includes a containment vessel having a drywell and a wetwell, a cooling condenser submerged in a cooling pool of water located outside the containment vessel, a vent line extending from the condenser to a suppr... | 09/09/2003 |
| 6594333 | Thermal load reducing system for nuclear reactor vessel The present invention is used to reduce thermal load itself, being the cause to generate stress, which develops near liquid surface in a nuclear reactor wall and to contribute to further improvement of safety. A partition member (5) is arranged above a co... | 07/15/2003 |
| 6519308 | Corrosion mitigation system for liquid metal nuclear reactors with passive decay heat removal systems A liquid metal nuclear reactor is described. The reactor includes a concrete reactor silo, and at least one primary vessel located in the reactor silo and coupled to a reactor shield deck. Each primary vessel is substantially surrounded by a containment v... | 02/11/2003 |
| 6269873 | Method for controlling heat exchange in a nuclear reactor A method for controlling heat exchange in a nuclear reactor. The reactor contains at least one thermal valve, at least one heat exchanger having a coolant flowing therein, with the heat exchanger being immersed in a pool containing a fluid. The heat excha... | 08/07/2001 |
| 6249561 | Combination containment cooling and residual heat removal condenser system for nuclear reactors Combination primary containment cooling system and residual heat removal steam condensers (PCCS-CND) operable in a containment cooling mode and in a reactor vessel cooling mode are described. In the containment cooling mode, the PCCS-CND interfaces with t... | 06/19/2001 |
| 6243432 | Modified passive containment cooling system for a nuclear reactor Modified passive containment cooling systems for cooling a reactor core of a boiling water nuclear reactor are described. The reactor core is positioned in a reactor pressure vessel which is located in a drywell of the nuclear reactor. The passive contain... | 06/05/2001 |
| 6160863 | Variable speed pump for use in nuclear reactor A nuclear reactor coolant system includes a primary coolant circuit connected to a secondary coolant circuit. A desired amount of coolant is bled from the primary circuit to the secondary circuit for purification and controlling chemical composition of th... | 12/12/2000 |
| 6069930 | Modified passive containment cooling system for a nuclear reactor Modified passive containment cooling systems for cooling a reactor core of a boiling water nuclear reactor are described. The passive containment cooling system (PCCS), in one form, includes a vent line coupled to the vacuum breaker. The vent line include... | 05/30/2000 |
| 6026138 | Method and device for safeguarding the discharge of residual heat from a reactor of a nuclear power station A method for safeguarding discharge of residual heat from a nuclear power station reactor upon a lowered filling level in a primary circuit of a reactor cooling system, includes initially shutting down the reactor and running through an initial cooling an... | 02/15/2000 |
| 5943384 | Depressurization system for pressurized steam operated plant A depressurization system (1) for pressurized steam operated plant employing injection of cold water contained in a superelevated tank (5), said injection being triggered rapidly and in a manner independent of the magnitude of the damage and of the presen... | 08/24/1999 |
| 5898748 | Vacuum breaker valve assembly Breaker valve assemblies for a simplified boiling water nuclear reactor are described. The breaker valve assembly, in one form, includes a valve body and a breaker valve. The valve body includes an interior chamber, and an inlet passage extends from the c... | 04/27/1999 |
| 5896431 | Systems and methods for preventing steam leakage between a drywell and a wetwell in a nuclear reactor Systems, methods, and apparatus for preventing steam leakage between a drywell and a wetwell in a nuclear reactor are described. In accordance with one embodiment of the present invention, the vacuum breaker of the nuclear reactor is coupled to a vacuum b... | 04/20/1999 |
| 5887043 | Passive emergency water system for water-cooled nuclear reactors A passive emergency water system for cooling the atmosphere inside containment in a water-cooled nuclear reactor comprises an elevated in-containment water reservoir connected to an in-containment heat exchanger. The heat exchanger promotes natural convec... | 03/23/1999 |
| 5828714 | Enhanced passive safety system for a nuclear pressurized water reactor A passive safety system for a nuclear reactor coolant system including a water storage tank, a heat exchanger positioned within the water storage tank and connected to the hot leg, and a core make-up tank having a tank inlet connected to the heat exchange... | 10/27/1998 |
| 5825838 | Reactor flooding system for a retaining molten core materials in a reactor vessel by the improved external vessel cooling capability A reactor cavity flooding system, which is used to immerse the hemispherical lower head of a nuclear reactor vessel by flooding the reactor cavity, is connected to both coolant injection nozzles located at the annulus gap between the lower head and the th... | 10/20/1998 |
| 5790619 | Drain system for a nuclear power plant A drain system for a shutdown cooling system of a pressurized water reactor type of a nuclear power plant (10) has an increased flow rate in the drain pipe (28) and drain pump (33). The hot leg (18) connected drain pipe has a vaned vortex breaker (30) mou... | 08/04/1998 |
| 5761262 | Passive containment cooling system of nuclear reactor A passive containment cooling system for a nuclear reactor and a method of cooling a pressurized water reactor thereby has an isolation condensing means for cooling and condensing steam and accumulating and cooling noncondensable gas released from within ... | 06/02/1998 |
| 5748693 | Safety feed for borating system for a pressurized water reactor and process for operating such a system In the event of an incident in a pressurized water reactor with a safety feed and borating system, it is necessary that sufficient primary cooling water be available in the reactor cooling system or be resupplied, and it must also be possible to render th... | 05/05/1998 |
| 5699394 | Thermal insulating barrier and neutron shield providing integrated protection for a nuclear reactor vessel The reactor vessel of a nuclear reactor installation which is suspended from the cold leg nozzles in a reactor cavity is provided with a lower thermal insulating barrier spaced from the reactor vessel to form a chamber which can be flooded with cooling wa... | 12/16/1997 |
| 5694442 | System for passively dissipating heat from the interior of a nuclear reactor containment structure A system (10) for dissipating heat from the interior space (50) of a containment structure (3, 6) for a nuclear reactor (2), for an indefinite time period, comprises a first heat exchanger (15, 15') outside said containment structure (3, 6) which is subme... | 12/02/1997 |
| 5661770 | Passive emergency water system for water-cooled nuclear reactors A passive emergency water system for cooling the atmosphere inside containment in a water-cooled nuclear reactor comprises an elevated water reservoir connected to an in-containment heat exchanger. The heat exchanger promotes natural convection of contain... | 08/26/1997 |
| 5659591 | Containment spray system for a light-water reactor A containment spray system for a light-water reactor includes a water trough being disposed in a safety tank. An immersion pump disposed in the vicinity of the bottom of the water trough, a spray branch and an outlet-side spray nozzle array, are connected... | 08/19/1997 |
| 5642389 | Light water reactor in particular a boiling water reactor with a high degree of inherent safety A light water reactor, in particular a boiling water reactor, includes a reactor pressure vessel having an interior, a core disposed in a lower half of the pressure vessel, fuel assemblies disposed in the core, and a column of water covering the core and ... | 06/24/1997 |
| 5612982 | Nuclear power plant with containment cooling A passive nuclear power plant includes a reactor vessel enclosed by a containment shell. An in-containment cooling system piped with an out-of-containment heat sink, includes an in-containment heat exchanger vertically extending adjacent the sidewall of t... | 03/18/1997 |
| 5579355 | Heat dissipation system for a nuclear reactor, in particular a pressurized water reactor A nuclear reactor, in particular a pressurized water reactor, has a containment, a containment shell surrounding the containment and a concrete construction of a reactor building surrounding the containment shell. A heat dissipation system for the nuclear... | 11/26/1996 |
| 5517539 | Method of decontaminating a PWR primary loop In a method of decontaminating a primary loop of a pressurized water reactor, including a steam generator, reactor coolant pump and hot and cold legs in the loop, the primary loop is isolated from a nuclear reactor vessel by closing hot leg and cold leg l... | 05/14/1996 |
