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| Number | Title | Issue Date |
| 7340387 | Control rod driving simulator for verification of control rod driving mechanism control system of atomic power plant A control rod driving simulator has a control rod driving unit having a plurality of coil members vertically mounted therein, a control rod mounted vertically movably through the centers of the coil members, a cart having a reserve tank storing cooling water, a cool... | 03/04/2008 |
| 7325401 | Power conversion systems Power generation systems and methods are provided with features directed to various innovations including ones relating to the conversion of concentrated solar and biomass energy to electricity, load-shifting of electrical power supply systems, gas turbine devices a... | 02/05/2008 |
| 7325399 | Coolant penetrating cold-end pressure vessel An improvement is provided to a pressurized close-cycle machine that has a cold-end pressure vessel and is of the type having a piston undergoing reciprocating linear motion within a cylinder containing a working fluid heated by conduction through a heater head by h... | 02/05/2008 |
| 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 |
| 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 |
| 7158605 | Head assembly A head assembly for a reactor pressure vessel includes a removable closure head, an array of control rod drive mechanisms, a seismic support platform, a missile shield assembly and a cooling system for drawing atmospheric air across electromagnetic coil stack assemb... | 01/02/2007 |
| 7139359 | Integrated head assembly for a nuclear reactor An integrated head assembly (100) is disclosed for a nuclear reactor. The preferred integrated head assembly includes a lift assembly (150) that supports the reactor vessel closure head (90) and integrated head assembly for removal, a separate s... | 11/21/2006 |
| 7136449 | Nuclear reactor plant The invention provides a cooling system which includes at least one and preferably a plurality of coolant chambers arranged around a heat source, typically a nuclear reactor. A coolant inlet pipe enters the or each coolant chamber at a high level and extends downwar... | 11/14/2006 |
| 7046739 | Pre-distortion of input signals to form constant envelope signal outputs A plurality of input signals are pre-distorted for combination into a first combined signal having a constant envelop. The input signals are combined into a second combined signal, and a similarity between each of the input signals and the second combined signal is ... | 05/16/2006 |
| 6944255 | Nuclear reactor A nuclear reactor in which a secondary or tertiary coolant system of a nuclear steam supply system is simplified, comprising: a reactor vessel (2) which integrates a reactor core (1); a first coolant (3) which is stored in the reactor vessel ( | 09/13/2005 |
| 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 |
| 6885720 | Modular reactor containment system A compact metal containment vessel, for a boiling water nuclear reactor, includes in one exemplary embodiment, a bottom head, a removable top head, and a substantially cylindrical sidewall extending from the bottom head to the top head. The bottom head, top head and... | 04/26/2005 |
| 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 |
| 6639960 | Method of retrofitting a reactor pressure vessel head assembly A head assembly of a reactor pressure vessel in an ice condenser plant is retrofitted to permit the assembly to be removed during a later refueling operation in reduced time and with reduced exposure to radiation by operating personnel. The portions of th... | 10/28/2003 |
| 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 |
| 6333956 | Blow-off device and method of blowing off live steam A blow-off device for live steam includes a filter for radioactive substances in order to increase operational safety in a nuclear power plant. The filter is preferably integrated in a housing of a muffler or sound absorber and is disposed on a slide whic... | 12/25/2001 |
| 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 |
| 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 |
| 6240154 | Self-actuated louvers for venting a CEDM cooling system of a nuclear reactor and method of using the same An augmented cooling system for a CEDM in a nuclear reactor includes self actuated louvers or flap valve louvers which allow hot air from the head lift rig to vent and cooler ambient air to enter the rig in the event that pressure is lost for the forced c... | 05/29/2001 |
| 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 |
| 6071482 | Device for cooling and intermixing of gas from accidental leaks A device for the cooling and intermixing of gas from accidental leaks, such as from a nuclear reaction containment, i.e., accident atmospheres, which device prevents stratification and provides improved cooling capacity. The device includes a housing, hav... | 06/06/2000 |
| 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 |
| 6061415 | Missile shield for a nuclear reactor pressure vessel An integrated head assembly for a nuclear reactor pressure vessel includes a closure head with CRDM assemblies extending upwardly from the head. A CRDM seismic support disposed above the closure head provides lateral support for the CRDM assemblies. The s... | 05/09/2000 |
| 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 |
| 5930321 | Head assembly An integrated head assembly for a nuclear reactor pressure vessel includes a closure head with CRDM assemblies extending upwardly from the head. A CRDM seismic support disposed above the closure head provides lateral support for the CRDM assemblies. The s... | 07/27/1999 |
| 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 |
| 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 |
| 5742652 | Head assembly An integrated head assembly for a nuclear reactor pressure vessel includes a closure head with CRDM assemblies extending upwardly from the head. A CRDM seismic support disposed above the closure head provides lateral support for the CRDM assemblies. The s... | 04/21/1998 |
| 5740215 | System for backcooling radioactive-waste containers A transport/storage container holding spent radioactive fuel elements is cooled by withdrawing gases from inside the container to create a subatmospheric pressure therein, feeding coolant water from a reservoir into the container, withdrawing steam from t... | 04/14/1998 |
| 5740217 | Passive emergency hydrogen mitigation system for water-cooled nuclear reactors An improved system for passively removing hydrogen inside containment in a nuclear reactor in the event of a loss of coolant accident by means of catalytic hydrogen recombination. A baffle wall located inside containment is used to establish within contai... | 04/14/1998 |
| 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 |
| 5689538 | Device and method for recovering and cooling the molten core of a nuclear reactor The device includes a corium collector arranged below the vessel of the reactor, with circulation channels for cooling the collector and the corium. These channels are connected to a water feed and cooling-fluid removal circuit including a water storage t... | 11/18/1997 |
| 5684846 | Nuclear reactor plant having containment isolation A nuclear reactor plant has a nuclear reactor vessel in a containment vessel. Air ducts, sump discharge lines, service water lines and other non-process non-critical lines extending through the wall of the containment vessel can be isolated passively (i.e... | 11/04/1997 |
