Class / Patent application number | Description | Number of patent applications / Date published |
376395000 | Having specified fluid flow path or pattern within reactor core | 17 |
20080279326 | NUCLEAR REACTOR DOWNCOMER FLOW DEFLECTOR - A nuclear reactor having a coolant flow deflector secured to a reactor core barrel in line with a coolant inlet nozzle. The flow deflector redirects incoming coolant down an annulus between the core barrel and the reactor vessel. The deflector has a main body with a front side facing the fluid inlet nozzle and a rear side facing the core barrel. The rear side of the main body has at least one protrusion secured to the core barrel so that a gap exists between the rear side of the main body adjacent the protrusion and the core barrel. Preferably, the protrusion is a relief that circumscribes the rear side of the main body. | 11-13-2008 |
20110222642 | SFR NUCLEAR REACTOR OF THE INTEGRATED TYPE WITH IMPROVED COMPACTNESS AND CONVECTION - The invention relates to a novel architecture for a nuclear reactor of the integrated type. | 09-15-2011 |
20120155600 | FUEL BUNDLE FLOW LIMITER - A fuel bundle flow limiter according to a non-limiting embodiment of the present invention may include a plurality of base sections, wherein each of the plurality of base sections has at least one opening. A plurality of channels may separate the plurality of base sections. A plurality of vertical webs may extend from the plurality of base sections. A locking tab may be disposed in at least one of the plurality of vertical webs. By using the flow limiter, the moisture carry over (MCO) level at the exit of the fuel bundle may be decreased, thereby reducing radiation exposure to plant operators and reducing damage to reactor equipment. | 06-21-2012 |
20130235968 | REACTOR VESSEL COOLANT DEFLECTOR SHIELD - A power module includes a reactor vessel containing a coolant and a reactor core located near a bottom end of the reactor vessel. A riser section is located above the reactor core, wherein the coolant circulates past the reactor core and up through the riser section. In one embodiment, a coolant deflector shield includes flow-optimized surfaces, wherein the flow-optimized surfaces direct the coolant towards the bottom end of the reactor vessel. In another embodiment, the reactor housing includes an inward facing portion that varies a flow pressure of the coolant and promotes a circulation of the coolant past a baffle assembly and towards the bottom end of the reactor vessel. | 09-12-2013 |
20130308740 | PRESSURIZER SURGE-LINE SEPARATOR FOR INTEGRAL PRESSURIZED WATER REACTORS - An integral pressurized light water reactor having most of the components of a primary side of a pressurized water reactor nuclear steam supply system housed in a single pressure vessel with a pressurizer separated from the remaining reactor system by a surge separator having multiple layers of separated steel plates with a number of concentric baffles extending therebetween. A circuitous flow path is provided through and between the plates and concentric baffles and a relatively stagnant pool of coolant is maintained within an innermost zone between the plates to provide thermal isolation. | 11-21-2013 |
20140037038 | PRESSURIZED WATER REACTOR - A pressurized water reactor comprises a reactor pressure vessel ( | 02-06-2014 |
20140140467 | PRESSURIZED WATER REACTOR WITH INTERNAL REACTOR COOLANT PUMP SYSTEM - A pressurized water reactor (PWR) includes a pressure vessel containing a radioactive core immersed in primary coolant water. A reactor coolant pump (RCP) disposed in a downcomer annulus of the PWR includes a jet pump and an electric pump whose impeller is disposed at the jet pump injector inlet. The electric pump includes a canned electric motor that is disposed in the downcomer annulus. In another RCP embodiment, the jet pump is omitted and the electric pump is seated in a flow distributor with the impeller of the seated RCP disposed in an impeller plenum defined by the flow distributor. The flow distributor further defines a fluid flow path with one or more branches extending from an inlet and running alongside but not through the canned electric motor of the seated RCP to discharge into the impeller plenum containing the impeller of the seated RCP. | 05-22-2014 |
20140334594 | NUCLEAR REACTOR PRIMARY CIRCUIT, WITH A BRANCH EQUIPPED WITH A THERMAL SLEEVE - A nuclear reactor primary circuit with a branch equipped with a thermal sleeve is provided. The nuclear reactor primary circuit includes a primary tubing, having an inner surface delimiting an inner volume in which a primary fluid circulates for cooling the nuclear reactor; a branch fastened to the primary tubing and delimiting an inner passage communicating with the inner volume of the primary tubing; a sleeve, having a first end connected to the branch and a second free end engaged in the inner volume of the primary tubing, the second end protruding in the inner volume relative to the inner surface over a non-zero length, an annular space being delimited between the sleeve and the branch. The primary circuit comprises a device making the sleeve unlosable, the unlosability device comprising at least one first raised portion formed on the branch, at least one second raised portion formed on the sleeve and capable of cooperating with the first raised portion to prevent the sleeve from falling into the primary tubing if the sleeve separates from the branch. | 11-13-2014 |
20150092905 | Feed water distributing system for a nuclear power plant, and method for operating a nuclear power plant - A feed water distributing system for a nuclear power plant contains feed water distributers disposed within a reactor pressure vessel. The feed water distributing system has a consistent feed water distribution when starting up and during a partial load operation with low mechanical loads and has a redundancy of the individual components while maintaining the customary level of reliability in nuclear power plants. Each feed water distributer has exactly one annular main body with an inner channel, at least one fill socket which is fluidically connected to the inner channel via at least one fill opening, and a plurality of outlet nozzles which are fluidically connected to the inner channel. Each of the fill sockets of one feed water distributer is fluidically connected to each outlet nozzle of the feed water distributer. | 04-02-2015 |
376396000 | Plural separate coolant loops through reactor core | 3 |
20120170705 | OPTIMUM CONFIGURATION FOR FAST REACTORS - A nuclear reactor having a liquid metal or molten salt coolant in a riser space | 07-05-2012 |
20120263270 | COMPACT INTEGRAL PRESSURIZED WATER NUCLEAR REACTOR - A pressurized water reactor (PWR) includes a cylindrical pressure vessel defining a sealed volume, a nuclear reactor core disposed in a lower portion of the cylindrical pressure vessel, one or more control rod drive mechanisms (CRDMs) disposed in the cylindrical pressure vessel above the nuclear reactor core, and an annular steam generator surrounding the nuclear reactor core and the CRDM. In some such PWR, a cylindrical riser is disposed coaxially inside the pressure vessel and inside the annular steam generator and surrounds the nuclear reactor core and the CRDM, and the steam generator is disposed coaxially inside the cylindrical pressure vessel in an annular volume defined by the cylindrical pressure vessel and the cylindrical riser. In other such PWR, the steam generator is disposed coaxially outside of and secured with the cylindrical pressure vessel. | 10-18-2012 |
20160012923 | NUCLEAR REACTOR SHROUD | 01-14-2016 |
376399000 | With particular flow directing or diverting means (e.g., flow baffle) | 5 |
20100322369 | LIQUID COOLED NUCLEAR REACTOR WITH ANNULAR STEAM GENERATOR - A nuclear reactor in which a primary coolant is contained, the primary coolant moves upwardly from the core by an operation thereof. An annular steam generator is arranged in an upper side of the core into which the upwardly moving primary coolant flows and transfers heat in the primary coolant into water therein to generate a steam. A passage structure defines a coolant passage for the primary coolant to an outside of the core. The heat-transferred primary coolant in the annular steam generator flows downwardly in the coolant passage so as to flow into the core, thereby moving upwardly. A reactor vessel is arranged to surround the coolant passage so as to contain the core, the annular steam generator and the passage means therein. | 12-23-2010 |
20120155601 | FLOW TRIPPING DEVICE - A flow tripping device according to a non-limiting embodiment of the present invention may include a peripheral band surrounding a central space. A plurality of flow tabs may extend from an upper portion of the peripheral band toward the central space. A plurality of finger structures may extend from a lower portion of the peripheral band. When installed in a fuel channel of a boiling water reactor (BWR), the critical power ratio (CPR) performance of the periphery rods may be increased, thereby also increasing overall performance. Consequently, the increased power translates to lower fuel cycle costs. | 06-21-2012 |
20120294410 | PRESSURIZER BAFFLE PLATE AND PRESSURIZED WATER REACTOR (PWR) EMPLOYING SAME - A pressurized water reactor (PWR) includes a pressure vessel and a nuclear reactor core disposed in the pressure vessel. A baffle plate is disposed in the pressure vessel and separates the pressure vessel into an internal pressurizer volume disposed above the baffle plate and an operational PWR volume disposed below the baffle plate. The baffle plate comprises first and second spaced apart plates and includes a pressure transfer passage having a lower end in fluid communication with the operational PWR volume and an upper end in fluid communication with the internal pressurizer volume at a level below an operational pressurizer liquid level range. A vent pipe has a lower end in fluid communication with the operational PWR volume and an upper end in fluid communication with the internal pressurizer volume at a level above the operational pressurizer liquid level range. | 11-22-2012 |
20150310943 | PRESSURIZED WATER REACTOR FLOW SKIRT APPARATUS - A pressurized water reactor vessel having a flow skirt formed from a perforated cylinder structure supported in the lower reactor vessel head at the outlet of the downcomer annulus, that channels the coolant flow through flow holes in the wall of the cylinder structure. The flow skirt is supported at a plurality of circumferentially spaced locations on the lower reactor vessel head that are not equally spaced or vertically aligned with the core barrel attachment points, and the flow skirt employs a unique arrangement of hole patterns that assure a substantially balanced pressure and flow of the coolant over the entire underside of the lower core support plate. | 10-29-2015 |
20150357059 | FLOW ALLOCATION APPARATUS, LOWER REACTOR INTERNAL OF REACTOR, AND REACTOR - A flow distribution device ( | 12-10-2015 |