| Class / Patent application number | Description | Number of patent applications / Date published |
|---|
| 376366000 | Plural fluids or a fluid in plural phases circulating within reactor (e.g., pressure tube reactors) | 49 |
| 20100124306 | REACTOR VESSEL REFLECTOR WITH INTEGRATED FLOW-THROUGH - A nuclear reactor module includes a reactor core and a reactor housing that surrounds the reactor core about its sides, wherein the reactor housing is configured to direct coolant through the reactor core. A neutron reflector is located between the reactor core and the reactor housing, wherein the neutron reflector has a plurality of inlet ports facing the reactor core. The neutron reflector also has a plurality of outlet ports fluidly connected to the inlet ports to direct a portion of the coolant through the neutron reflector. | 05-20-2010 |
| 20130089174 | PRESSURE-TUBE REACTOR WITH COOLANT PRENUM - A pressure-tube nuclear reactor can include an outer shell having an interior to contain a moderator at a first pressure and a coolant plenum to receive the coolant fluid at a second pressure, the second pressure being greater than the first pressure. The reactor also includes a plurality of pressure tubes. Each pressure tube is received within and extends through a corresponding shell tube and is configured to releasably retain at least one fuel bundle. A first end of each pressure tube being coupled to the plenum tubesheet in fluid communication with the plenum chamber and a second end of each pressure tube fluidly connected to a coolant conduit to enable the coolant fluid to flow between the coolant plenum and each pressure tube and to flow from the nuclear reactor for further processing. | 04-11-2013 |
| 20130170602 | METHOD AND APPARATUS FOR A HIGH-TEMPERATURE DEPOSITION SOLUTION INJECTOR - A method and apparatus for a deposition solution injector for a nuclear reactor that may inject an ambient temperature deposition solution into a high temperature, high pressure feed-water flow line. The method and the apparatus ensures that the deposition solution is delivered in a location within the feed-water that is beyond a boundary layer of flowing water, to prevent smearing of the solution and prevent clogging of the deposition solution within the injector. The axial cross-sectional profile of the injector, and the location of an injection slot on the injector, may reduce vortex eddy flow of the feed-water into the injector to further reduce injector blockage. | 07-04-2013 |
| 376367000 | In heat pipe means | 8 |
| 20090285348 | Heat pipe fission fuel element - Illustrative embodiments provide nuclear fission fuel elements, and systems, applications, apparatuses, and methods related thereto. Illustrative embodiments and aspects include, without limitation, nuclear fission fuel elements, heat pipe assemblies, heat pipes, methods of fabricating a nuclear fission fuel element, methods of fabricating a heat pipe assembly, and the like. | 11-19-2009 |
| 20090285349 | Heat pipe fission fuel element - Illustrative embodiments provide nuclear fission fuel elements, and systems, applications, apparatuses, and methods related thereto. Illustrative embodiments and aspects include, without limitation, nuclear fission fuel elements, heat pipe assemblies, heat pipes, methods of fabricating a nuclear fission fuel element, methods of fabricating a heat pipe assembly, and the like. | 11-19-2009 |
| 20090290676 | NUCLEAR-ENGINEERING PLANT AND METHOD OF OPERATING A NUCLEAR-ENGINEERING PLANT - A nuclear-engineering installation has a pressurized-water reactor and a degasification system for reactor coolant. The degasification system has a degasification column which is coupled to the primary cooling circuit of the pressurized water reactor and further includes a coolant evaporator with a first heat exchanger and a stripping vapor condenser with a second heat exchanger, wherein a partial flow of the reactor coolant flows through the heat exchanger of the coolant evaporator on the secondary side, and wherein the heat exchanger of the stripping vapor condenser is connected, on the primary side, in a vapor and gas outlet line which is connected to the degasifier column. The degasification system is intended to be configured such that, with as simple a design as possible and taking into consideration relevant safety procedures, a particularly effective and at the same time energy-efficient separation of gasses, which are dissolved in the reactor coolant and cannot be condensed, is made possible, wherein the thermal load of the assigned nuclear intermediate cooling system is furthermore intended to be kept as low as possible. To this end it is provided that the heat exchanger of the coolant evaporator is switched in a heat-pump circuit on the primary side, which heat-pump circuit is coupled to the heat exchanger of the stripping vapor condenser with respect to the heat flux, which is established during plant operation, such that the heat liberated in the strip steam condensation is transferred at least partially to the reactor coolant, which flows through the coolant evaporator, and thus causes its evaporation. | 11-26-2009 |
| 20100040187 | Heat pipe nuclear fission deflagration wave reactor cooling - Illustrative embodiments provide systems, applications, apparatuses, and methods related to nuclear fission deflagration wave reactor cooling. Illustrative embodiments and aspects include, without limitation, nuclear fission deflagration wave reactors, methods of transferring heat of a nuclear fission deflagration wave reactor, methods of transferring heat from a nuclear fission deflagration wave reactor, methods of transferring heat within a nuclear fission deflagration wave reactor, and the like. | 02-18-2010 |
| 20100040188 | Heat pipe nuclear fission deflagration wave reactor cooling - Illustrative embodiments provide systems, applications, apparatuses, and methods related to nuclear fission deflagration wave reactor cooling. Illustrative embodiments and aspects include, without limitation, nuclear fission deflagration wave reactors, methods of transferring heat of a nuclear fission deflagration wave reactor, methods of transferring heat from a nuclear fission deflagration wave reactor, methods of transferring heat within a nuclear fission deflagration wave reactor, and the like. | 02-18-2010 |
| 20100208861 | Method and system for providing fuel in a nuclear reactor - Exemplary embodiments provide automated nuclear fission reactors and methods for their operation. Exemplary embodiments and aspects include, without limitation, re-use of nuclear fission fuel, alternate fuels and fuel geometries, modular fuel cores, fast fluid cooling, variable burn-up, programmable nuclear thermostats, fast flux irradiation, temperature-driven surface area/volume ratio neutron absorption, low coolant temperature cores, refueling, and the like. | 08-19-2010 |
| 20120082286 | METHODS AND APPARATUSES FOR REMOVAL AND TRANSPORT OF THERMAL ENERGY - Methods and apparatuses are provided for the removal and transportation of thermal energy from a heat source to a distant complex for use in thermochemical cycles or other processes. In one embodiment, an apparatus includes a hybrid heat pipes/thermosyphon intermediate heat exchanger (HPTIHX) system that is divided into three distinct sections, namely: an evaporation chamber, a condensation chamber, and a working fluid transport section of liquid and vapor counter-current flows. | 04-05-2012 |
| 20160196885 | STEAM GENERATOR FOR NUCLEAR STEAM SUPPLY SYSTEM | 07-07-2016 |
| 376370000 | With formation, separation, or manipulation of a vapor (e.g., boiling water reactor (BWR) type) | 38 |
| 20110051880 | High Efficiency Power Plants - Modified Kalina and modified Mayahi cycle heat engines are disclosed. Improvements in efficiency may be gained through various changes to these cycles as well as combining these cycles with boiling water reactors and other Rankine cycle power plants. | 03-03-2011 |
| 20120269314 | HIGH-TEMPERATURE GAS-COOLED REACTOR STEAM GENERATING SYSTEM AND METHOD - A high-temperature gas-cooled reactor steam generating system comprises a plurality of nuclear steam supply systems, a high-pressure cylinder ( | 10-25-2012 |
| 20150332793 | Natural-Circulation Boiling Water Reactor and Chimney Therefor - The present invention provides a chimney for a natural-circulation boiling water reactor having structural soundness capable of standing a horizontal load generated by a flow-induced vibration, an earthquake and the like. The chimney for a natural-circulation boiling water reactor according to the present invention is characterized in that: the chimney is disposed in the inside of a reactor pressure vessel, and includes plural flow channels which guide a steam-water two-phase flow generated in a reactor core to the upper part of the reactor pressure vessel; each of the flow channels is formed partitioned by plural flow channel separation walls whose lower-most part is supported by a chimney lattice plate; and chimney spacers that support the horizontal load each other are arranged between the flow channel separation walls of the adjacent flow channels, and ring-like members that support the horizontal load are arranged at the outermost periphery of the plural flow channels that are supported by the chimney lattice plate. | 11-19-2015 |
| 20160379724 | PART INCLUDING VIBRATION MITIGATION DEVICE(S), NUCLEAR REACTOR PRESSURE VESSEL ASSEMBLY INCLUDING THE PART, AND METHODS OF MANUFACTURING THEREOF - A nuclear reactor pressure vessel assembly includes a part in a reactor housing structure. The part includes a body a vibration absorber. The body includes an internal surface. The internal surface of the body defines at least one cavity that is not exposed to an environment external to the body. The vibration absorber includes at least one of a harmonic oscillator connected to the internal surface of the body or an external surface of the body, a shear multiplier in the at least one cavity, a hybrid mass-viscoelastic structure in the at least one cavity and not secured to the internal surface of the body, and a distributed damping structure incorporated into the body. | 12-29-2016 |
| 376371000 | With vapor-liquid separating means | 6 |
| 20090092218 | Steam Dryer for Reactor Pressure Vessel - A steam dryer through which steam flows vertically, in particular for a nuclear reactor, contains a plurality of water tanks for removing water which has been separated from the steam. The water tanks are disposed below dryer elements through which the steam flows. The water tanks of the steam dryer have in each case in the flow direction a cross section which is favorable in terms of flow. | 04-09-2009 |
| 20090274261 | STEAM DRYER - A steam dryer includes a plurality of steam dryer banks. Each steam dryer bank includes a hood, separator vanes, and a perforated plate connected to the hood to define a volume configured to receive a flow of steam. Each dryer bank forms a closed loop. | 11-05-2009 |
| 20110064183 | METHODS FOR STABILIZING A STEAM DRYER ASSEMBLY IN A NUCLEAR REACTOR PRESSURE VESSEL - A device and method for stabilizing a dryer assembly in a reactor pressure vessel of a nuclear reactor including a spring assembly dimensioned and positioned within the reactor pressure vessel for applying a stabilizing force to the dryer assembly relative to the reactor pressure vessel. | 03-17-2011 |
| 20130028366 | STEAM SEPARATOR AND NUCLEAR REACTOR SYSTEM USING THE SAME - According to an embodiment, a steam separator is provided with a barrel, a swirler, a pick-off ring, a steam collecting pipe and transverse pipes. A two-phase flow of steam and water ascends inside the barrel. The two-phase flow has a swirl force imparted by the swirler. Flow near the inner surface of the barrel is separated by the pick-off ring, etc. from flow near the center of the barrel and is guided so as to descend along the outer surface of the barrel. A major part of the flow near the center of the barrel is separated from the outside flow by the steam collecting pipe and guided to the outside of the barrel through the transverse pipes. | 01-31-2013 |
| 20150310944 | STEAM SEPARATION SYSTEM AND NUCLEAR BOILING WATER REACTOR INCLUDING THE SAME - In one embodiment, the steam separation system includes a plurality of steam separators configured to separate liquid from a gas-liquid two-phase flow stream; and a steam dryer system disposed above the steam separators. The steam dryer system includes a plurality of steam dryer bank assemblies and at least one moisture trap. Each of the steam dryer bank assemblies is configured to separate liquid of the gas-liquid two-phase flow stream exiting the steam separators. The moisture trap is disposed next to one of the steam dryer bank assemblies and is configured to remove liquid from the gas-liquid two-phase flow stream. | 10-29-2015 |
| 20160189810 | SWIRLER, STEAM SEPARATOR INCLUDING THE SWIRLER, AND NUCLEAR BOILING WATER REACTOR INCLUDING THE SAME - In one embodiment, the steam separator includes a standpipe configured to receive a gas-liquid two-phase flow stream, and a first swirler configured to receive the gas-liquid two-phase flow stream from the standpipe. The first swirler is configured to separate the gas-liquid two-phase flow stream. The first swirler includes a direct flow portion and an indirect flow portion. The direct flow portion has a direct flow channel for permitting direct flow of the gas-liquid two-phase flow stream through the first swirler, and the indirect flow portion has at least one indirect flow channel defined by at least one vane in the first swirler for providing an indirect flow of the gas-liquid two-phase flow stream through the first swirler. | 06-30-2016 |
| 376372000 | With jet pump | 24 |
| 20080205578 | APPARATUS AND METHOD FOR REINFORCING JET PUMP RISER - An apparatus for reinforcing a jet pump riser includes: an elbow upper clamp for covering a riser elbow coupled to a thermal sleeve from an upper side thereof; an elbow lower clamping member for clamping the riser elbow from a lower side thereof; an elbow vertical portion clamping member for covering a vertical portion of the riser elbow; and an elbow horizontal portion clamping member for covering a horizontal portion of the riser elbow. These members are disposed in different orientations with respect to the elbow upper clamp so as to fix the thermal sleeve, the riser elbow and the riser pipe. | 08-28-2008 |
| 20100150299 | METHOD AND APPARATUS FOR EXECUTING AN OPERATION IN A PRESSURE VESSEL OF A NUCLEAR REACTOR - An operation method and apparatus in a pressure vessel of a nuclear reactor is provided. The operation apparatus including a body and a guide inserted from the upper side of the nuclear reactor to an interior of the jet pump. The operation apparatus circulate water inside the pressure vessel. The guide is positioned at the end of a body of the operation apparatus, and is inclined with respect to the center axis of the body so as to be inserted into a side opening of the jet pump. | 06-17-2010 |
| 20100266093 | Methods and apparatuses for clamping a jet pump sensing line support - Example embodiment clamps may be used to clamp two components together, with a degree of freedom of motion between the clamped components, including both rotational and translational motion. Example embodiment clamps may clamp a BWR jet pump sensing line to a diffuser as a repair or installation of a sensing line support. Example clamps may include a ball subassembly that holds a component and allows rotation and twisting of the component within the clamp. Example clamps may further include jaws holding the ball subassembly and a biasing element that permits tightening of the clamp. | 10-21-2010 |
| 20100316181 | INTEGRAL HELICAL COIL PRESSURIZED WATER NUCLEAR REACTOR - An integral pressurized water nuclear reactor for the production of steam utilizing a helical coil steam generator, a plurality of internal circulation pumps, and an internal control rod drive mechanism structure. | 12-16-2010 |
| 20100329412 | SYSTEM FOR DAMPENING VIBRATION - An embodiment of the present invention takes the form of a system that may reduce the level of flow-induced vibration (FIV) experienced by a jet pump assembly or other similar object within a pressure vessel. Essentially, an embodiment of the present invention may reduce the slip-joint leakage, which may be a cause of the FIVs, by adding a flow-limiting component to an outlet of the slip joint. This component may take the form of a collar, channel, and/or other component that may be connectable to a component of the jet pump assembly. After installation, an embodiment of the present invention may lower the amplitude of, and/or change the frequency of, the FIVs experienced by the jet pump assembly. | 12-30-2010 |
| 20110069804 | Jet Pump Slip Joint Modification for Vibration Reduction - A method for retrofitting a boiling water reactor slip joint of a jet pump to reduce vibrations is provided. The method includes removing a mixing chamber from an existing slip joint defined by a diffuser and the mixing chamber, the existing slip joint defining an existing annular gap, and providing a new slip joint defining a new annular gap, the new annular gap being reshaped to permit reduced vibration. A jet pump and a method of operating a jet pump are also provided. | 03-24-2011 |
| 20110135049 | APPARATUS AND SYSTEM FOR RESTRICTING THE MOVEMENT OF A COMPONENT - An embodiment of the present invention provides an apparatus and system for repairing and/or maintaining a position of a first component in relation to a second component. The first and second components may be located within a reactor pressure vessel of a nuclear powerplant. The apparatus and system may attach at least one bearing plate to a horizontal surface of the first component. The apparatus and system includes structure to apply a pre-load to the first component. This may assist in maintaining the position of the first component relative to the second component. | 06-09-2011 |
| 20110255649 | JET PUMP BEAM AND METHOD FOR PRODUCING THE SAME - A jet pump beam is made of improved heat-treated precipitation-hardened nickel base alloy excellent in anti-stress corrosion cracking properties and high-temperature strength, and having high ductility and a high elastic modulus. A jet pump beam | 10-20-2011 |
| 20110280360 | WEDGE POSITIONING APPARATUS FOR JET PUMP ASSEMBLIES IN NUCLEAR REACTORS - An auxiliary wedge positioning apparatus/assembly | 11-17-2011 |
| 20110299650 | APPARATUS AND METHOD FOR REPAIRING RISER PIPE ELBOW WELD IN BOILING WATER NUCLEAR REACTOR - A support clamp assembly for mechanically securing a thermal sleeve to an elbow conduit in a jet pump of a nuclear reactor vessel, the support clamp assembly including: a tension shaft having a first end extendable through an opening in a sidewall of the elbow conduit and an opposite end with a head; a cruciform assembly having a base with an opening to receive the tension shaft and to abut the head of the shaft, wherein the cruciform assembly seats in the thermal sleeve; a boss slidable over the first end of the tension shaft and having a curved surface seating an outside surface of the elbow conduit, and a coupling device engaging the first end of the tension shaft and abutting the boss, wherein the coupling device places the tension shaft under tension to secure the cruciform assembly to the thermal sleeve and the boss to the elbow conduit. | 12-08-2011 |
| 20120014495 | MULTI-STAGE JET PUMP MIXER ASSEMBLY - A boiling water nuclear reactor (BWR) multi-stage jet pump mixer assembly according to a non-limiting embodiment of the present invention may include at least one nozzle disposed above a first throat structure which is arranged within a second throat structure. The multi-stage jet pump mixer assembly is configured such that when a drive flow is discharged from the nozzle into the first throat structure, a first suction stage occurs in that a first entrained flow is drawn into the first entrainment entrance and forms a mixed flow. The mixed flow exiting the first throat structure then induces a second entrained flow into the second entrainment entrance during a second suction stage. By employing a multi-stage approach, jet pump efficiency may be improved. | 01-19-2012 |
| 20120027158 | JET PUMP AND METHOD FOR RESTRAINING VIBRATION OF THE SAME - The present invention has an object to provide a jet pump, which can restrain self-excited vibration in a connection portion between an inlet mixer pipe and a diffuser pipe without inhibiting a structural deformation due to thermal expansion and the like. | 02-02-2012 |
| 20120033781 | METHOD AND APPARATUS FOR A BWR INLET MIXER CLAMP ASSEMBLY - A method and apparatus for physically restraining an inlet mixer of a boiling water reactor (BWR) jet pump assembly. An inlet mixer clamp assembly is attached to the top of a transition piece of the BWR jet pump assembly, to provides a downward clamping force on the top of the inlet mixer. The clamping force restrains the inlet mixer from experiencing vibration and mitigates leakage between the inlet mixer and the transition piece sealing surfaces of the jet pump assembly. The clamping force also restrains the inlet mixer from undesirable rotation, especially during operation of the jet pump assembly. The inlet mixer clamp assembly may be used as an alternative to conventional jet pump beam assemblies. Alternatively, the inlet mixer clamp assembly may be used as a redundant physical restraint in addition to the conventional jet pump beam assemblies. | 02-09-2012 |
| 20120033782 | METHOD AND APPARATUS FOR A BWR JET PUMP INLET MIXER SUPPORT - A method and apparatus for a Boiling Water Reactor (BWR) jet pump inlet mixer support that provides rigid support for inlet mixers. The inlet mixer support attaches to a conventional BWR jet pump assembly to pull the inlet mixer away from the centerline of a riser pipe or maintain the existing inlet mixer position. The inlet mixer support may provide redundant support that may otherwise be provided by set screws of a conventional restrainer assembly. The inlet mixer support may, alternatively, be used in lieu of conventional set screws. The inlet mixer support may also counter-act additional side loading that may be applied to inlet mixers to stabilize inlet mixer movement and vibration when the BWR jet pump assembly is in operation. Optionally, the inlet mixer support may also prevent removal of existing restrainer bracket set screws. | 02-09-2012 |
| 20120163527 | ADJUSTABLE HARD STOPS FOR NUCLEAR REACTOR RESTRAINER BRACKETS AND METHODS OF USING THE SAME - Hard stops are useable in an operating nuclear reactor to separate and bias restrainer brackets and inlet mixers. Hard stops include a lip clamp that clamps to a restrainer bracket and a wedge member that biases against the inlet mixer. The wedge member and lip clamp are engaged such that the two components can slide against one another to bias the restrainer bracket and inlet mixer. The lip clamp includes a clamp arm and an engagement member to clamp opposite sides of the restrainer bracket. Ratchet assemblies maintain selective positioning various components of the hard stops. Hard stops may be used in several different numbers, positions, and configurations in repair or modification systems. Hard stops may be installed by determining location on an outside of a restrainer bracket for the hard stop, securing the hard stop at the location, and biasing the hard stop between two components at the location. | 06-28-2012 |
| 20120170703 | Method and apparatus for a jet pump inlet mixer integral slip joint clamp - A method and apparatus for providing a Boiling Water Reactor (BWR) jet pump inlet-mixer integral slip joint clamp to constrain the inlet mixer and diffuser to mitigate inlet mixer flow induced vibration of a BWR jet pump assembly. The slip joint clamp includes horizontally projecting flanges with vertical sidewalls that protrude toward a lowest distal end of the inlet mixer. Fasteners penetrating the flanges provide a biasing load on the diffusers by being tightened to press against an upper crown on the diffuser. One or more flanges may be used. Laterally disposed gaps between the flanges may provide a clearance for guide ears of the diffuser to fit between the flanges. | 07-05-2012 |
| 20120170704 | METHOD AND APPARATUS FOR A JET PUMP THREE POINT SLIP JOINT CLAMP - A method and apparatus for providing a Boiling Water Reactor (BWR) jet pump three point slip joint clamp to mitigate sleep joint leakage flow induced vibration of a BWR jet pump assembly. A collar, provided as one seamless component or in separate portions, is installed on the upper crown of a diffuser. The collar includes a lower set of fasteners and an upper set of fasteners that contact the inlet mixer and diffuser, respectively, to horizontally stabilize the inlet mixer in a fixed position inside of the diffuser. The upper fasteners may be anchored by bosses that ensure a light-weight design of the collar. An optional cantilevered seal (including a cantilevered overhang and a lip) may mitigate leakage from the slip joint interface. | 07-05-2012 |
| 20120219103 | VIBRATION REDUCTION TECHNIQUES FOR JET PUMP SLIP JOINTS - A method for retrofitting a boiling water reactor is provided. The method includes removing a mixing chamber from a slip joint defined by a diffuser and the mixing chamber, the mixing chamber having an inner surface and a bottom edge directing flow to the diffuser such that a recirculation zone at an entrance to the slip joint creates a diverging effective path for the leakage flow entering the slip joint. The method also includes providing a new inner surface and new bottom edge, the new inner surface and the new bottom edge being reshaped to decrease the size of the recirculation zone. A jet pump is also provided. | 08-30-2012 |
| 20130028367 | PRESSURIZED WATER REACTOR WITH REACTOR COOLANT PUMPS OPERATING IN THE DOWNCOMER ANNULUS - A pressurized water reactor (PWR) includes a vertical cylindrical pressure vessel and a nuclear reactor core disposed in a lower vessel section. A hollow cylindrical central riser is disposed concentrically inside the pressure vessel. A downcomer annulus is defined between the central riser and the pressure vessel. A reactor coolant pump (RCP) includes (i) an impeller disposed above the nuclear reactor core and in fluid communication with the downcomer annulus to impel primary coolant downward through the downcomer annulus, (ii) a pump motor disposed outside of the pressure vessel, and (iii) a drive shaft operatively connecting the pump motor with the impeller. The PWR may include an internal steam generator in the downcomer annulus, with the impeller is disposed below the steam generator. The impeller may be disposed in the downcomer annulus. The RCP may further comprise a pump casing that with the impeller defines a centrifugal pump. | 01-31-2013 |
| 20130308739 | APPARATUSES AND METHODS FOR CONTROLLING MOVEMENT OF COMPONENTS - An apparatus for controlling movement of a first component integrated with a second component may include a first clamp configured to engage the first component, a second clamp configured to engage the second component, and a plurality of connectors configured to connect the first and second clamps. The connectors may allow movement of the first clamp relative to the second clamp in a first direction between the first and second clamps. The connectors may limit movement of the first clamp relative to the second clamp in a second direction perpendicular to the first direction. | 11-21-2013 |
| 20130315365 | METHOD AND APPARATUS FOR A JET PUMP INLET-MIXER SLIP JOINT - A slip joint of the jet pump assembly inlet-mixer is the interface between a diffuser and an inlet-mixer. The diffuser is coated with a first hardfacing alloy, and the inlet-mixer is coated with a second hardfacing alloy different from the first hardfacing alloy. The first hardfacing alloy may be a cobalt-based alloy and the second hardfacing alloy may be a cobalt-free alloy, i.e., at least one of an iron-based and nickel-based hardfacing alloy. | 11-28-2013 |
| 20140177778 | JET PUMP BEAM WELDLESS KEEPER LOCK PLATE - A lock plate for a locking device of a jet pump beam, the locking device including a locking sleeve including a lower portion, may include a beam bolt opening sized to receive the locking sleeve, and a spring arm including plurality of spring a ratchet teeth sized to mesh with locking sleeve ratchet teeth included in the lower portion of the locking sleeve, the spring arm being structured such that the spring arm has both i) an engaged position where the locking sleeve is in the beam bolt opening and at least a portion of the capture feature overlaps vertically with an upper surface of the lower portion of the locking sleeve, and ii) a disengaged position where the locking sleeve is in the beam bolt opening and the capture feature does not overlap vertically with the upper surface. | 06-26-2014 |
| 20150016583 | METHOD OF REPAIRING JET PUMP MEASURING PIPE AND REPAIR DEVICE THEREFOR - A jet pump measuring pipe repair method that repairs a ruptured part of a measuring pipe horizontally installed to a lower portion of a jet pump provided in reactor water inside a reactor pressure vessel. The repair method includes: fixing a support member to the jet pump near the measuring pipe left remained; mounting, after the support member fixing, a measuring pipe connector provided with a pipe-repairing pipe having both ends over which connecting pipes are fitted, respectively, to the support member; connecting, after the connector mounting, the remaining measuring pipe and connecting pipe using the measuring pipe connector. | 01-15-2015 |
| 20160093408 | JET PUMP FOR BOILING WATER REACTOR AND BOILING WATER REACTOR - The present embodiments provide a jet pump for a boiling water reactor as well as a boiling water reactor equipped with the jet pump, the jet pump being less prone to cause self-excited vibration in the case of both forward leakage flow and backward leakage flow. A jet pump | 03-31-2016 |
| 376373000 | Having specified fluid flow path or pattern within reactor core | 2 |
| 20140112428 | SYSTEM AND METHOD FOR COOLING VIA PHASE CHANGE - The present invention relates generally to the field of cooling systems and/or methods for cooling a heated, fissioning, or exothermic solution. In one embodiment, the present invention relates to a cooling system, and method of utilizing same, for cooling a heated, fissioning, or exothermic solution that utilizes submerged cooling coils where the system of the present invention relies on a combination of multiple factors to achieve the desired effect. In one embodiment, the present invention relates to a cooling system, and method of utilizing same, for cooling a heated, fissioning, or exothermic solution that utilizes submerged cooling coils where the system of the present invention relies on the combination of: (i) cooling coil geometry; (ii) cooling coil location and design; and (iii) cooling coil operational pressure. | 04-24-2014 |
| 376377000 | With particular flow directing or diverting means (e.g., flow baffle) | 1 |
| 20100284507 | NUCLEAR REACTOR - In a nuclear reactor, a core barrel ( | 11-11-2010 |
| 376378000 | Vapor manipulated or used exterior of reactor core | 2 |
| 20110116591 | 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. | 05-19-2011 |
| 20130279643 | Steam Generator for a Nuclear Reactor - A steam generator for a nuclear reactor comprises plenums proximate with a first plane, wherein the first plane intersects a bottom portion of a riser column of a reactor vessel. The steam generator may further comprise plenums proximate with a second plane, approximately parallel with the first plane, wherein the second plane intersects a top portion of the riser column of the reactor vessel. The steam generator may further include a plurality of steam generator tubes that convey coolant from a plenum located proximate with the first plane to one of the plenums proximate with the second plane. | 10-24-2013 |
