A system, apparatus, method, and non-transitory computer readable medium for performing improved and/or optimal sensor placement may include a computing device caused to, receive a plurality of fault conditions and an initial sensor suite associated with at least one object to be simulated, the initial sensor suite including a plurality of candidate physical sensors for the at least one object, perform failure mode analysis of the initial sensor suite, the performing the failure mode analysis including generating at least one dependency-matrix (D-matrix) based on the plurality of fault conditions and the plurality of candidate physical sensors, and generate a recommended sensor suite associated with the at least one object based on results of the failure mode analysis, the recommended sensor suite including at least one recommended sensor, the at least one recommended sensor being a subset of the plurality of candidate physical sensors.
A system, apparatus, method, and non-transitory computer readable medium for performing improved and/or optimal sensor placement may include a computing device caused to, receive a plurality of fault conditions and an initial sensor suite associated with at least one object to be simulated, the initial sensor suite including a plurality of candidate physical sensors for the at least one object, perform failure mode analysis of the initial sensor suite, the performing the failure mode analysis including generating at least one dependency-matrix (D-matrix) based on the plurality of fault conditions and the plurality of candidate physical sensors, and generate a recommended sensor suite associated with the at least one object based on results of the failure mode analysis, the recommended sensor suite including at least one recommended sensor, the at least one recommended sensor being a subset of the plurality of candidate physical sensors.
Nuclear reactors have very few systems for significantly reduced failure possibilities. Nuclear reactors may be boiling water reactors with natural circulation-enabling heights and smaller, flexible energy outputs in the 0-350 megawatt-electric range. Reactors are fully surrounded by an impermeable, high-pressure containment. No coolant pools, heat sinks, active pumps, or other emergency fluid sources may be present inside containment; emergency cooling, like isolation condenser systems, are outside containment. Isolation valves integral with the reactor pressure vessel provide working and emergency fluid through containment to the reactor. Isolation valves are one-piece, welded, or otherwise integral with reactors and fluid conduits having ASME-compliance to eliminate risk of shear failure. Containment may be completely underground and seismically insulated to minimize footprint and above-ground target area.
G21C 1/02 - Fast fission reactors, i.e. reactors not using a moderator
G21C 1/08 - Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling-water reactor, integral-superheat reactor, pressurised-water reactor
An integrated nuclear-powered heat pump system includes a nuclear power plant including a nuclear reactor coolant and may be configured to generate electricity. The system additionally includes a heat pump including a refrigerant as a working fluid. The heat pump is integrated with the nuclear power plant so as to be in at least thermal contact with the nuclear reactor coolant. The electricity generated by the nuclear power plant may be used to drive the heat pump. The system is instrumental with regard to generating heat for industrial applications.
F22B 1/16 - Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being hot liquid or hot vapour, e.g. waste liquid, waste vapour
E21B 43/24 - Enhanced recovery methods for obtaining hydrocarbons using heat, e.g. steam injection
F25B 1/10 - Compression machines, plants or systems with non-reversible cycle with multi-stage compression
F25B 9/00 - Compression machines, plants or systems, in which the refrigerant is air or other gas of low boiling point
G21D 5/06 - Reactor and engine not structurally combined with engine working medium circulating through reactor core
G21D 9/00 - Arrangements to provide heat for purposes other than conversion into power, e.g. for heating buildings
5.
MULTI-MODE HEAT REMOVAL SYSTEMS FOR NUCLEAR REACTORS AND METHODS OF USING THE SAME
Piping loops can carry either forced or natural circulation coolant flow from and back to a reactor depending on reactor and coolant state, and can transition between the two. The loop flows into a heat exchanger that significantly cools the coolant and may even condense the coolant. The heat exchanger can drive natural circulation coolant flow, and a pump on the loop can drive forced circulation. Coolant direction may be reversed through the heat exchanger in different modes. Loops may be installed directly on existing ICSs, come off of a primary loop generating electricity commercially, or be their own loop around and penetrations to the reactor. Actuation valves may isolate and actuate the system merely by disallowing or allowing coolant flow. Different flow modes and coolant direction may be similarly achieved by pump actuation and/or valve opening/closing. Beyond the pump and simple valve actuation, loops may be entirely passive.
The method includes generating first temperature data at a first temperature sensor based on a temperature of a first flowstream of a coolant fluid in a flow channel and heat transfer to the first temperature sensor from a heating element, the heating element being coupled to the first temperature sensor at an interface, the first temperature data indicating a first temperature measured by the first temperature sensor, generating second temperature data at a second temperature sensor based on a temperature of a second flowstream of the coolant fluid in the flow channel and independently of heat generated by the heating element, the first flowstream and the second flowstream running parallel to each other, the second temperature sensor being insulated from the heating element, the second temperature data indicating a second temperature measured by the second temperature sensor.
G21C 17/022 - Devices or arrangements for monitoring coolant or moderator for monitoring liquid coolants or moderators
G01F 1/68 - Measuring the volume flow or mass flow of fluid or fluent solid material wherein the fluid passes through a meter in a continuous flow by using thermal effects
G21C 17/032 - Reactor-coolant flow measuring or monitoring
G21C 17/10 - Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
A Modular Isolated Reactor Support System (MIRSS) assembly includes a cylindrical reactor support structure configured to structurally support a reactor enclosure system on seismic isolators, a collector cylinder configured to at least partially define a riser annulus between an inner cylindrical surface of the collector cylinder and an outer sidewall surface of the reactor enclosure system structurally supported by the cylindrical reactor support structure, and a divider wall configured to at least partially define a downcomer annulus between an outer cylindrical surface of the divider wall and a reactor building, and a plurality of exhaust ducts extending from the collector cylinder and through an interior of the cylindrical reactor support structure.
G21C 11/08 - Thermal shields; Thermal linings, i.e. for dissipating heat from gamma radiation which would otherwise heat an outer biological shield
G21C 15/02 - Arrangement or disposition of passages in which heat is transferred to the coolant, e.g. for coolant circulation through the supports of the fuel elements
8.
METHODS AND SYSTEMS FOR PREDICTING FATIGUE ACCUMULATION
A method of identifying at least one critical location on a physical structure includes receiving operational information related to an operation of the physical structure, the operational information including different time instances of the operation of the physical structure and the operation of the physical structure at different operational levels; predicting damage to the physical structure based on the operational information, predicted operation of the physical structure with at least one of the different operational levels, and at least one model of the physical structure such that initiation of the damage at a plurality of locations of the physical structure is predicted independent of a proximity of the sensors to each of the plurality of locations; and identifying the at least one critical location on the physical structure based on the predicted damage.
A Modular Isolated Reactor Support System (MIRSS) assembly includes a cylindrical reactor support structure configured to structurally support a reactor enclosure system on seismic isolators, a collector cylinder configured to at least partially define a riser annulus between an inner cylindrical surface of the collector cylinder and an outer sidewall surface of the reactor enclosure system structurally supported by the cylindrical reactor support structure, and a divider wall configured to at least partially define a downcomer annulus between an outer cylindrical surface of the divider wall and a reactor building, and a plurality of exhaust ducts extending from the collector cylinder and through an interior of the cylindrical reactor support structure.
E04H 9/02 - Buildings, groups of buildings or shelters adapted to withstand or provide protection against abnormal external influences, e.g. war-like action, earthquake or extreme climate withstanding earthquake or sinking of ground
G21C 13/024 - Supporting constructions for pressure vessels or containment vessels
F16F 15/02 - Suppression of vibrations of non-rotating, e.g. reciprocating, systems; Suppression of vibrations of rotating systems by use of members not moving with the rotating system
10.
METHODS AND SYSTEMS FOR PREDICTING FATIGUE ACCUMULATION
A method of identifying at least one critical location on a physical structure includes receiving operational information related to an operation of the physical structure, the operational information including different time instances of the operation of the physical structure and the operation of the physical structure at different operational levels; predicting damage to the physical structure based on the operational information, predicted operation of the physical structure with at least one of the different operational levels, and at least one model of the physical structure such that initiation of the damage at a plurality of locations of the physical structure is predicted independent of a proximity of the sensors to each of the plurality of locations; and identifying the at least one critical location on the physical structure based on the predicted damage.
A sodium-cooled nuclear reactor includes at least one electromagnetic pump assembly and a backflow reduction pipe. The backflow reduction pipe may include an inlet, an outlet, at least one tubular section having a first length and a first diameter, and at least one fluid diode section between the inlet and the outlet.
An electromagnetic pump (EMP 120) for a liquid metal-cooled nuclear reactor (110) includes a pump casing (302), concentric inner and outer flow ducts (310) collectively defining a flow annulus (312) extending coaxially with a longitudinal axis of the EMP, and induction coils (320) configured to control the flow of liquid metal coolant through the flow annulus based on electrical power received from the power supply (144). At least one of the inner flow duct (310-1) or the outer flow duct (310-2) includes a gamma shielding material (414, 424) configured to block gamma rays from entering an interior of the EMP from the flow annulus. The pump casing may include a neutron absorber material (434) configured to absorb neutrons entering the pump casing from an exterior of the EMP. The EMP may include a neutron moderator material (452) on an outer surface of the pump casing and configured to moderate neutrons entering the pump casing to be absorbed by the neutron absorber material.
G21C 1/32 - Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core
13.
SYSTEMS AND METHODS OF THERMOELECTRIC COOLING IN POWER PLANTS
Systems and methods provide a thermoelectric cooler to cool a variety of high-energy power plant geometries and configurations. The thermoelectric cooler is thermally connected at heat sink side to a component to be cooled, including coolant structural components, for the plant. A heat rejection side of the cooler is thermally connected to a heat sink, including ambient air, a plant structure, or a fluid coolant. Electricity may be selectively applied to the cooler to generate a temperature difference and heat flux between the heat sinking side and heat rejection side. Radiation-resilient materials may be used in the cooler in the case of nuclear installations. Power sources include batteries, plant or grid electrical power, dedicated generators, or any other power source, potentially at relatively low ratings, such as only hundreds of watts, that will provide desired thermoelectric cooling.
G21C 15/02 - Arrangement or disposition of passages in which heat is transferred to the coolant, e.g. for coolant circulation through the supports of the fuel elements
F25B 21/02 - Machines, plants or systems, using electric or magnetic effects using Nernst-Ettinghausen effect
Jet pump clamps fit to modified jet pump assemblies at the riser pipe-restrainer bracket junction. The clamp can secure the restrainer bracket and riser pipe, relieving any welds between the same stress in the same, while preventing the restrainer bracket from moving. The clamp may include multiple members on either side of the restrainer bracket that fit into surfaces of the riser pipe. When these members are drawn together through clamping action, the underlying riser pipe is compressed. Similarly, vertically-adjustable members may seat into and/or through the restrainer bracket to hold the bracket steady. Jet pump assemblies may be prepared by forming grooves in the riser pipe and hole(s) in the restrainer bracket(s) and spherical indentations about the same. Clamps may then be installed on the grooves and through the hole(s) at installation or during a maintenance outage in a commercial nuclear power plant.
F04F 5/44 - Component parts, details, or accessories not provided for in, or of interest apart from, groups
F16B 2/06 - Clamps, i.e. with gripping action effected by positive means other than the inherent resistance to deformation of the material of the fastening external, i.e. with contracting action
G21C 15/25 - Promoting flow of the coolant for liquids using jet pumps
15.
JET PUMP CLAMPS AND METHODS FOR USE IN A NUCLEAR REACTOR JET PUMP
Jet pump clamps fit to modified jet pump assemblies at the riser pipe-restrainer bracket junction. The clamp can secure the restrainer bracket and riser pipe, relieving any welds between the same stress in the same, while preventing the restrainer bracket from moving. The clamp may include multiple members on either side of the restrainer bracket that fit into surfaces of the riser pipe. When these members are drawn together through clamping action, the underlying riser pipe is compressed. Similarly, vertically-adjustable members may seat into and/or through the restrainer bracket to hold the bracket steady. Jet pump assemblies may be prepared by forming grooves in the riser pipe and hole(s) in the restrainer bracket(s) and spherical indentations about the same. Clamps may then be installed on the grooves and through the hole(s) at installation or during a maintenance outage in a commercial nuclear power plant.
F16B 2/06 - Clamps, i.e. with gripping action effected by positive means other than the inherent resistance to deformation of the material of the fastening external, i.e. with contracting action
G21C 15/243 - Promoting flow of the coolant for liquids
A nuclear power plant includes a nuclear structure, a frontline support equipment, and a support structure. The nuclear structure includes, and is configured to protect from incurring damage due to a damaging event, at least one of a nuclear reactor or a nuclear fuel storage. The frontline support equipment is configured to perform a fundamental safety function. The support structure is spatially separate from the nuclear structure and includes an initiating support equipment configured to trigger the frontline support equipment to perform the fundamental safety function such that the fundamental safety function is performed independently of the initiating support equipment subsequent to the triggering. The support structure may be a non-protected structure that is not configured to protect the initiating support equipment from incurring damage due to the damaging event.
An electromagnetic pump (EMP) for a liquid metal-cooled nuclear reactor includes a pump casing, concentric inner and outer flow ducts collectively defining a flow annulus extending coaxially with a longitudinal axis of the EMP, and induction coils configured to control the flow of liquid metal coolant through the flow annulus based on electrical power received from the power supply. At least one of the inner flow duct or the outer flow duct includes a gamma shielding material configured to block gamma rays from entering an interior of the EMP from the flow annulus. The pump casing may include a neutron absorber material configured to absorb neutrons entering the pump casing from an exterior of the EMP. The EMP may include a neutron moderator material on an outer surface of the pump casing and configured to moderate neutrons entering the pump casing to be absorbed by the neutron absorber material.
An integrated nuclear-powered heat pump system includes a nuclear power plant including a nuclear reactor coolant and may be configured to generate electricity. The system additionally includes a heat pump including a refrigerant as a working fluid. The heat pump is integrated with the nuclear power plant so as to be in at least thermal contact with the nuclear reactor coolant. The electricity generated by the nuclear power plant may be used to drive the heat pump. The system is instrumental with regard to generating heat for industrial applications.
Clamp systems include multiple, separate clamps joinable to components subject to relative rotation. Clamps may have similarly-positioned features to simplify installation and/or removal about a small area for all clamps in the system. Each clamp cannot freely rotate relative to an adjacent clamp but does not pass vertical loads to an adjacent clamp. Clamps may use mating shapes like an extension and recess to limit rotation. Clamps fit to the perimeters of components to which they individually secure by biasing against the components. At least one clamp has a transitional surface to provide space between the clamp and component to provide containment to a weld or other joining structure. Clamp systems can be tightened by included fasteners. Crimp nuts or other locking structures can preserve the biased and secured nature of the clamps and underlying structures. Clamp systems may be used to secure or repair a lifting rod assembly.
F16B 2/06 - Clamps, i.e. with gripping action effected by positive means other than the inherent resistance to deformation of the material of the fastening external, i.e. with contracting action
G21C 19/20 - Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
20.
PROCESS AND TOOLS TO PERFORM REACTOR PRESSURE VESSEL NOZZLE EXPANSION MITIGATING PRIMARY COOLANT LEAKAGE
A nozzle expansion tool includes a frame with a drive system on the frame. A rotary mandrel is drivingly connected to the drive system and is engageable with an expansion roller device. A plurality of vacuum cups are mounted to the frame and each include a vacuum fitting adapted to be connected to a vacuum source. A depth adjustment mechanism is connected to the expansion roller device and is configured to adjust a distance that the expansion roller device extends from the frame.
G21C 19/20 - Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
G21C 9/00 - Emergency protection arrangements structurally associated with the reactor
21.
PROCESS AND TOOLS TO PERFORM REACTOR PRESSURE VESSEL NOZZLE EXPANSION MITIGATING PRIMARY COOLANT LEAKAGE
A nozzle expansion tool includes a frame with a drive system on the frame. A rotary mandrel is drivingly connected to the drive system and is engageable with an expansion roller device. A plurality of vacuum cups are mounted to the frame and each include a vacuum fitting adapted to be connected to a vacuum source. A depth adjustment mechanism is connected to the expansion roller device and is configured to adjust a distance that the expansion roller device extends from the frame.
Systems reduce noncondensable gasses within coolant systems with a recombiner into which the fluid coolant flows. Flow through the recombiner may be opposite that of a heat exchanger. The recombiner includes a catalyst that combines or degrades the noncondensable gasses, such as a Group 9-11 transition metal that speeds reaction of noncondensable gasses. The catalyst may be a liner, plate, aggregate, et. with openings through which all coolant must flow. The recombiner may be insulated to prevent heat exchange and condensation and may be tilted from a vertical to enhance draining and fluid flow. The entire system may be passive without any operator intervention or moving structures. Systems can be made from isolation condenser systems in nuclear power plants in an isolation condenser pool by adding a recombiner to existing coolant systems. Systems may also be made by including a recombiner with new isolation condensers.
Systems reduce noncondensable gasses within coolant systems with a recombiner into which the fluid coolant flows. Flow through the recombiner may be opposite that of a heat exchanger. The recombiner includes a catalyst that combines or degrades the noncondensable gasses, such as a Group 9-11 transition metal that speeds reaction of noncondensable gasses. The catalyst may be a liner, plate, aggregate, et. with openings through which all coolant must flow. The recombiner may be insulated to prevent heat exchange and condensation and may be tilted from a vertical to enhance draining and fluid flow. The entire system may be passive without any operator intervention or moving structures. Systems can be made from isolation condenser systems in nuclear power plants in an isolation condenser pool by adding a recombiner to existing coolant systems. Systems may also be made by including a recombiner with new isolation condensers.
G21C 15/16 - Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants comprising means for separating liquid and steam
G21C 15/02 - Arrangement or disposition of passages in which heat is transferred to the coolant, e.g. for coolant circulation through the supports of the fuel elements
A liquid metal-cooled nuclear reactor (110) includes, within a reactor pressure vessel (111) having a reactor core (112), a multistage annular linear induction pump (ALIP, 120) configured to circulate liquid metal coolant (190) through the reactor core. The multistage ALIP includes multiple sets of induction coils that at least partially define separate, respective stages (330-1 to 330-N) of the multistage ALIP. The multiple sets of induction coils are configured to be electrically connected to separate, respective polyphase power supplies (144-1 to 144-N), such that the stages of the multistage ALIP are configured to be controlled independently of each other to adjustably control a flow of liquid metal coolant through the reactor core based on independent control of the multiple polyphase power supplies.
A liquid metal-cooled nuclear reactor (110) includes, within a reactor pressure vessel (111) having a reactor core (112), a multistage annular linear induction pump (ALIP, 120) configured to circulate liquid metal coolant (190) through the reactor core. The multistage ALIP includes multiple sets of induction coils that at least partially define separate, respective stages (330-1 to 330-N) of the multistage ALIP. The multiple sets of induction coils are configured to be electrically connected to separate, respective polyphase power supplies (144-1 to 144-N), such that the stages of the multistage ALIP are configured to be controlled independently of each other to adjustably control a flow of liquid metal coolant through the reactor core based on independent control of the multiple polyphase power supplies.
A method of measuring moisture carryover (MCO) in a nuclear reactor includes placing a first gamma detector adjacent to a steam conduit configured to transport steam generated by the core. The method additionally includes detecting a first amount of carryover gamma activity of a first quantity of sodium-24 in the steam within the steam conduit with the first gamma detector. The method also includes detecting a second amount of reference gamma activity of a second quantity of sodium-24 in a reference sample of reactor water from the core with a second gamma detector. The method further includes determining a flow rate of liquid water entrained in the steam based on the first amount of carryover gamma activity detected by the first gamma detector and the second amount of reference gamma activity detected by the second gamma detector.
Clamp systems include multiple, separate clamps joinable to components subject to relative rotation. Clamps may have similarly-positioned features to simplify installation and/or removal about a small area for all clamps in the system. Each clamp cannot freely rotate relative to an adjacent clamp but does not pass vertical loads to an adjacent clamp. Clamps may use mating shapes like an extension and recess to limit rotation. Clamps fit to the perimeters of components to which they individually secure by biasing against the components. At least one clamp has a transitional surface to provide space between the clamp and component to provide containment to a weld or other joining structure. Clamp systems can be tightened by included fasteners. Crimp nuts or other locking structures can preserve the biased and secured nature of the clamps and underlying structures. Clamp systems may be used to secure or repair a lifting rod assembly.
F16B 2/06 - Clamps, i.e. with gripping action effected by positive means other than the inherent resistance to deformation of the material of the fastening external, i.e. with contracting action
G21C 19/20 - Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
28.
COOLANT CLEANUP AND HEAT-SINKING SYSTEMS AND METHODS OF OPERATING THE SAME
Combined cleanup and heat sink systems work with nuclear reactor coolant loops. Combined systems may join hotter and colder sections of the coolant loops in parallel with any steam generator or other extractor and provide optional heat removal between the same. Combined systems also remove impurities or debris from a fluid coolant without significant heat loss from the coolant. A cooler in the combined system may increase in capacity or be augmented in number to move between purifying cooling and major heat removal from the coolant, potentially as an emergency cooler. The cooler may be joined to the hotter and colder sections through valved flow paths depending on desired functionality. Sections of the coolant loops may be fully above the cooler, which may be above the reactor, to drive flow by gravity and enhance isolation of sections of the coolant loop.
G21C 19/307 - Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products specially adapted for liquids
Control rod drives include linearly-moveable control elements inside an isolation barrier. Control rod drives move the control element through secured magnetic elements subject to magnetic fields. Induction coils may generate the magnetic fields across a full stroke length of the control element in the reactor. A closed coolant loop may cool the induction coils, which may be in a vacuum outside the isolation barrier. A control rod assembly may house the magnetic elements and directly, removably join to the control element. The control rod assembly may lock with magnetic overtravel latches inside the isolation barrier to maintain an overtravel position. Overtravel release coils outside the isolation barrier may release the latches to leave the overtravel position. Methods of operation include selectively energizing or de-energizing induction coils to drive the control element to desired insertion points, including full insertion by gravity following de-energization. No direct connection may penetrate the isolation barrier.
A liquid metal-cooled nuclear reactor includes, within a reactor pressure vessel having a reactor core, a multistage annular linear induction pump (ALIP) configured to circulate liquid metal coolant through the reactor core. The multistage ALIP includes multiple sets of induction coils that at least partially define separate, respective stages of the multistage ALIP. The multiple sets of induction coils are configured to be electrically connected to separate, respective polyphase power supplies, such that the stages of the multistage ALIP are configured to be controlled independently of each other to adjustably control a flow of liquid metal coolant through the reactor core based on independent control of the multiple polyphase power supplies.
Steam generators in power plants exchange energy from a primary medium to a secondary medium for energy extraction. Steam generators include one or more primary conduits and one or more secondary conduits. The conduits do not intermix the mediums and may thus discriminate among different fluid sources and destinations. One conduit may boil feedwater while another reheats steam for use in lower and higher-pressure turbines, respectively. Valves and other selectors divert steam and/or water into the steam generator or to other turbines or the environment for load balancing and other operational characteristics. Conduits circulate around an interior perimeter of the steam generator immersed in the primary medium and may have different cross-sections, radii, and internal structures depending on contained. A water conduit may have less flow area and a tighter coil radius. A steam conduit may include a swirler and rivulet stopper to intermix water in any steam flow.
F01K 7/38 - Steam engine plants characterised by the use of specific types of engine; Plants or engines characterised by their use of special steam systems, cycles or processes; Control means specially adapted for such systems, cycles or processes; Use of withdrawn or exhaust steam for feed-water heating the engines being of extraction or non-condensing type; Use of steam for feed-water heating the engines being of turbine type
G21D 5/16 - Liquid working medium vaporised by reactor coolant superheated by separate heat source
F22B 1/02 - Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers
F01K 19/00 - Regenerating or otherwise treating steam exhaust from steam engine plant
F01K 7/34 - Steam engine plants characterised by the use of specific types of engine; Plants or engines characterised by their use of special steam systems, cycles or processes; Control means specially adapted for such systems, cycles or processes; Use of withdrawn or exhaust steam for feed-water heating the engines being of extraction or non-condensing type; Use of steam for feed-water heating
F01K 7/44 - Use of steam for feed-water heating and another purpose
F01K 11/02 - Steam engine plants characterised by the engines being structurally combined with boilers or condensers the engines being turbines
G21D 5/12 - Liquid working medium vaporised by reactor coolant
G21D 1/00 - NUCLEAR POWER PLANT - Details of nuclear power plant
32.
APPARATUSES FOR STEAM SEPARATION, AND NUCLEAR BOILING WATER REACTORS INCLUDING THE SAME
According to at least some example embodiments, a dome collector separation stage includes an inner side wall that defines an inner channel; and an outer side wall that, together with the inner side wall, defines an outer channel, the inner channel being configured to receive a two-phase flow stream (FS) of water and steam, and pass the two-phase FS to the outer channel via inlets included in the inner side wall, the outer channel being configured to separate at least some water from the two-phase FS, and pass moisture-reduced steam out of the steam separator stage via outlets included in the outer side wall.
G21C 15/16 - Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants comprising means for separating liquid and steam
F22B 37/28 - Steam-separating arrangements involving reversal of direction of flow
33.
Passive containment cooling system for a nuclear reactor
A nuclear plant includes a nuclear reactor, a containment structure that at least partially defines a containment environment of the nuclear reactor, and a passive containment cooling system that causes coolant fluid to flow downwards from a coolant reservoir to a bottom of a coolant channel coupled to the containment structure and rise through the coolant channel toward the coolant reservoir due to absorbing heat from the nuclear reactor. A check valve assembly, in fluid communication with the coolant reservoir, selectively enables one-way flow of a containment fluid from the containment environment to the coolant reservoir, based on a pressure at an inlet being equal to or greater than a threshold magnitude. A fusible plug, in fluid communication with the coolant reservoir at a bottom vertical depth below the bottom of the coolant reservoir, enables coolant fluid to flow into the containment structure based on at least partially melting.
F16K 17/38 - Safety valves; Equalising valves actuated in consequence of extraneous circumstances, e.g. shock, change of position of excessive temperature
G21C 9/02 - Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse
G21C 9/033 - Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse by an absorbent fluid
G21C 15/20 - Partitions or thermal insulation between fuel channel and moderator, e.g. in pressure tube reactors
34.
NUCLEAR REACTOR FACILITY INTEGRATED WITH PASSIVE AIR COOLING SYSTEM
A nuclear reactor facility may include a reactor building, a reactor vessel housed within the reactor building, and an auxiliary cooling system integrated with the reactor building. The reactor building has a visible section above a ground level and a buried section below the ground level. The reactor vessel contains a fuel core and is housed within the buried section of the reactor building below the ground level. The auxiliary cooling system includes a plurality of ducts integrated with the reactor building and is configured to passively cool the reactor vessel via natural air circulation.
G21C 13/073 - Closures for reactor-vessels, e.g. rotatable
G21C 15/12 - Arrangement or disposition of passages in which heat is transferred to the coolant, e.g. for coolant circulation through the supports of the fuel elements from containment vessel
A nuclear power plant includes a nuclear structure, a frontline support equipment, and a support structure. The nuclear structure includes, and is configured to protect from incurring damage due to a damaging event, at least one of a nuclear reactor or a nuclear fuel storage. The frontline support equipment is configured to perform a fundamental safety function. The support structure is spatially separate from the nuclear structure and includes an initiating support equipment configured to trigger the frontline support equipment to perform the fundamental safety function such that the fundamental safety function is performed independently of the initiating support equipment subsequent to the triggering. The support structure may be a non-protected structure that is not configured to protect the initiating support equipment from incurring damage due to the damaging event.
A nuclear power plant includes a nuclear structure, a frontline support equipment, and a support structure. The nuclear structure includes, and is configured to protect from incurring damage due to a damaging event, at least one of a nuclear reactor or a nuclear fuel storage. The frontline support equipment is configured to perform a fundamental safety function. The support structure is spatially separate from the nuclear structure and includes an initiating support equipment configured to trigger the frontline support equipment to perform the fundamental safety function such that the fundamental safety function is performed independently of the initiating support equipment subsequent to the triggering. The support structure may be a non-protected structure that is not configured to protect the initiating support equipment from incurring damage due to the damaging event.
A nuclear reactor facility may include a reactor building, a reactor vessel housed within the reactor building, and an auxiliary cooling system integrated with the reactor building. The reactor building has a visible section above a ground level and a buried section below the ground level. The reactor vessel contains a fuel core and is housed within the buried section of the reactor building below the ground level. The auxiliary cooling system includes a plurality of ducts integrated with the reactor building and is configured to passively cool the reactor vessel via natural air circulation.
G21C 13/02 - Pressure vessels; Containment vessels; Containment in general - Details
G21C 13/073 - Closures for reactor-vessels, e.g. rotatable
G21C 15/12 - Arrangement or disposition of passages in which heat is transferred to the coolant, e.g. for coolant circulation through the supports of the fuel elements from containment vessel
A nuclear reactor facility may include a reactor building, a reactor vessel housed within the reactor building, and an auxiliary cooling system integrated with the reactor building. The reactor building has a visible section above a ground level and a buried section below the ground level. The reactor vessel contains a fuel core and is housed within the buried section of the reactor building below the ground level. The auxiliary cooling system includes a plurality of ducts integrated with the reactor building and is configured to passively cool the reactor vessel via natural air circulation.
A nuclear power plant includes a nuclear structure, a frontline support equipment, and a support structure. The nuclear structure includes, and is configured to protect from incurring damage due to a damaging event, at least one of a nuclear reactor or a nuclear fuel storage. The frontline support equipment is configured to perform a fundamental safety function. The support structure is spatially separate from the nuclear structure and includes an initiating support equipment configured to trigger the frontline support equipment to perform the fundamental safety function such that the fundamental safety function is performed independently of the initiating support equipment subsequent to the triggering. The support structure may be a non-protected structure that is not configured to protect the initiating support equipment from incurring damage due to the damaging event.
A combined blade guide and exchange tool, include a blade guide tool having a lower end and an upper end and a plurality of frame rails supporting a pair of lower collet housings at a lower end of the blade guide tool. A pair of fuel support grapple actuating rods are supported between the plurality of frame rails and have a first end engaging a pair of collets within the pair of lower collet housings and a second end disposed at the upper end of the blade guide tool. A blade exchange tool is releasably mounted to the upper end of the blade guide tool and includes a pair of upper collets for engaging the pair of fuel support grapple actuating rods. The blade exchange tool further including a slider and hook assembly attached to a cable guided by the blade exchange tool and adapted for engaging a control rod.
G21C 19/10 - Lifting devices or pulling devices adapted for co-operation with fuel elements or with control elements
G21C 19/105 - Lifting devices or pulling devices adapted for co-operation with fuel elements or with control elements with grasping or spreading coupling elements
G21C 19/20 - Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
41.
Integrated passive cooling containment structure for a nuclear reactor
An integrated passive cooling containment structure for a nuclear reactor includes a concentric arrangement of an inner steel cylindrical shell and an outer steel cylindrical shell that define both a lateral boundary of a containment environment of the nuclear reactor that is configured to accommodate a nuclear reactor and an annular gap space between the inner and outer steel cylindrical shells, a concrete donut structure at a bottom of the annular gap space, and a plurality of concrete columns spaced apart azimuthally around a circumference of the annular gap and extending in parallel from a top surface of the concrete donut structure to a top of the annular gap space. The outer and inner steel cylindrical shells and the concrete donut structure at least partially define one or more coolant channels extending through the annular gap space.
G21C 13/10 - Means for preventing contamination in event of leakage
G21C 15/12 - Arrangement or disposition of passages in which heat is transferred to the coolant, e.g. for coolant circulation through the supports of the fuel elements from containment vessel
E04H 7/18 - Containers for fluids or gases; Supports therefor mainly of concrete, e.g. reinforced concrete, or other stone-like material
G21C 13/028 - Seals, e.g. for pressure vessels or containment vessels
Control rod drives include all-digital monitoring, powering, and controlling systems for operating the drives. Each controlling system includes distinct microprocessor-driven channels that independently monitor and handle control rod drive position information reported from multiple position sensors per drive. Controlling systems function as rod control and information systems with top-level hardware interfaced with nuclear plant operators other plant systems. The top-level hardware can receive operator instructions and report control rod position, as well as report errors detected using redundant data from the multiple sensors. Positional data received from each drive is multiplexed across plural, redundant channels to allow verification of the system using independent position data as well as operation of the system should a single channel or detector fail. Control rod drives are capable of positioning and detecting position of control elements in fine increments, such as 3-millimeter increments, with plural position sensors that digitally report drive status and position.
A nuclear plant including a nuclear reactor and a natural circulation air cooling system configured to provide cooling of the nuclear reactor based on circulating ambient air from an air inlet opening to absorb nuclear reactor rejected heat through an outlet air opening, due to natural circulation of said ambient air induced by the ambient air absorbing said rejected heat, may further include a pile structure covering at least one opening of the air inlet opening or the air outlet opening. The pile structure may include a pile of packing objects covering the at least one opening, such that the at least one opening is obscured from direct exposure to the ambient environment by the pile of the packing objects.
A nuclear plant including a nuclear reactor and a natural circulation air cooling system configured to provide cooling of the nuclear reactor based on circulating ambient air from an air inlet opening to absorb nuclear reactor rejected heat through an outlet air opening, due to natural circulation of said ambient air induced by the ambient air absorbing said rejected heat, may further include a pile structure covering at least one opening of the air inlet opening or the air outlet opening. The pile structure may include a pile of packing objects covering the at least one opening, such that the at least one opening is obscured from direct exposure to the ambient environment by the pile of the packing objects.
A nuclear plant including a nuclear reactor and a natural circulation air cooling system configured to provide cooling of the nuclear reactor based on circulating ambient air from an air inlet opening to absorb nuclear reactor rejected heat through an outlet air opening, due to natural circulation of said ambient air induced by the ambient air absorbing said rejected heat, may further include a pile structure covering at least one opening of the air inlet opening or the air outlet opening. The pile structure may include a pile of packing objects covering the at least one opening, such that the at least one opening is obscured from direct exposure to the ambient environment by the pile of the packing objects.
Piping loops can carry either forced or natural circulation coolant flow from and back to a reactor (10) depending on reactor and coolant state, and can transition between the two. The loop flows into a heat exchanger (122) that significantly cools the coolant and may even condense the coolant. The heat exchanger (122) can drive natural circulation coolant flow, and a pump (150) on the loop can drive forced circulation. Coolant direction may be reversed through the heat exchanger (122) in different modes. Loops may be installed directly on existing ICSs, come off of a primary loop generating electricity commercially, or be their own loop. Actuation valves (101, 102, 115, 151) may isolate and actuate the system (100) merely by disallowing or allowing coolant flow. Different flow modes and coolant direction may be similarly achieved by pump actuation and/or valve opening/closing. Beyond the pump and simple valve actuation, loops may be entirely passive.
Cleanup systems include plural coolant inputs that are physically combined to create a single flow at a desired filtering temperature. Filter(s) are used to clean the coolant, and coolant flowing therethrough will damage the filter or not be adequately filtered if having temperature in excess of an operating temperature of the filter. The inputs have different temperatures, and mixing them creates a combined flow at a desired temperature. The amount of each flow is selected based on its individual temperature to achieve this desired temperature. The combined flow is then conditioned with the filter at an operable temperature and returned to the coolant origin for the inputs. No heat exchangers or heat loss to outside heat sinks are required. Cleanup systems may be used with any coolant loop, including Rankine-cycle electricity generation systems like nuclear power plants, combustion boilers, and steam generators, and heat transfer systems.
G21C 19/04 - Means for controlling flow of coolant over objects being handled; Means for controlling flow of coolant through channel being serviced
G21C 15/06 - Arrangement or disposition of passages in which heat is transferred to the coolant, e.g. for coolant circulation through the supports of the fuel elements from fissile or breeder material in fuel elements
Dual-mode heat removal system that allows first direction natural circulation flow through a heat exchanger during nuclear reactor emergency cooling and allows opposite direction forced flow through the heat exchanger during decay heat removal
Piping loops can carry either forced or natural circulation coolant flow from and back to a nuclear reactor depending on reactor and coolant state, and can transition between the two. The loop flows into a heat exchanger that cools the coolant and may even condense the coolant. The heat exchanger can drive natural circulation coolant flow, and a pump on the loop can drive forced circulation. Coolant direction may be reversed through the heat exchanger in different modes. Loops may be installed directly on existing isolation condenser systems or come off of a primary loop generating electricity commercially. Actuation valves may isolate and actuate the system merely by disallowing or allowing coolant flow. Different flow modes and coolant direction may be similarly achieved by pump actuation and/or valve opening/closing. Beyond the pump and simple valve actuation, loops may be entirely passive.
EDM assemblies mount on a machining surface and discharge rotating sub-electrodes against the surface. The sub-electrodes can also revolve about another shared axis while discharging. Rotation and revolution may be achieved with planetary gears fixed with the sub-electrodes and meshing with a stationary sun gear. Several sub-electrodes can be used in a single assembly. Downward movement of the sub-electrodes from a central shaft on the mount allows several inches of the surface to be machined. Assemblies are usable in a nuclear reactor during a maintenance period to machine a hole for a replacement manway cover underwater in the flooded reactor. The differing rotational movements and vertical movement can be independently controlled with separate motors in the assembly. Power and controls may be provided remotely through an underwater connection.
A feedwater sparger repair assembly includes a cover plate having a partial cylindrical shape and having a nozzle opening and a pair of bolt openings extending through the cover plate. A nozzle is attached to the cover plate and surrounds the nozzle opening. A pair of T-bolts extend through a respective one of the pair of bolt openings and each include a shank having a threaded portion extending from an exterior side of the cover plate and a partial cylindrical head portion disposed at an end of the shank on an interior side of the cover plate. A pair of nuts are engaged with the threaded portion of the pair of T-bolts. The feedwater sparger repair assembly is adapted to be mounted to an opening that is cut into a core spray pipe in order to repair/replace a sparger that becomes cracked.
The apparatus includes a flowmeter coupled a surface exposed to a flow channel. The flowmeter monitors a flow of coolant. The flowmeter includes a first temperature sensor that generates first temperature data based on measuring a first temperature of a first flowstream, a heating element coupled to the first temperature sensor where the heating element applies heat to the first temperature sensor through an interface, a second temperature sensor generates second temperature data based on measuring a second temperature of a second flowstream, the second temperature sensor being spaced apart from the heating element, and the second temperature sensor being at least partially insulated from the heating element so the second temperature data generated by the second temperature sensor is independent of heat generated by the heating element. A processor calculates a flowrate of the coolant based on the second temperature data and a temperature of the coolant fluid.
G01F 1/68 - Measuring the volume flow or mass flow of fluid or fluent solid material wherein the fluid passes through a meter in a continuous flow by using thermal effects
G21C 17/022 - Devices or arrangements for monitoring coolant or moderator for monitoring liquid coolants or moderators
G21C 17/032 - Reactor-coolant flow measuring or monitoring
G21C 17/10 - Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
52.
MODULAR MANUFACTURE, DELIVERY, AND ASSEMBLY OF NUCLEAR REACTOR BUILDING SYSTEMS
A nuclear reactor is constructed in sub-modules and super modules which are manufactured, packaged, and shipped to a construction site. At least some of the modules are packaged in suitable shielding containers or portions of containers, which may be steel. The modules are assembled on-site, and some of the modules remain within their respective shipping containers after assembly. One or more of the shipping containers may be used as concrete forms to support the pouring of concrete in between selected modules. The concrete may be used for structural support, shielding, or both.
A nuclear reactor is designed to allow efficient packing of components within the reactor vessel, such as by offsetting the core, and/or vertically stacking components. The in-vessel storage system can be separate from the support cylinder and these components can be fabricated and shipped separately and coupled together at the construction site. Furthermore, the in-vessel storage system can be located adjacent to the core rather than being located circumferentially around it, and may also be located beneath the heat exchanger to further improve packing of components within the vessel. Through these, and other changes, the delicate components can be manufactured in a manufacturing facility, assembled, and shipped by commercial transportation options without exceeding the shipping envelope.
A method and apparatus of limiting power of a boiling water nuclear reactor system includes a reactor pressure vessel, a reactor core disposed in the reactor pressure vessel, a core shroud surrounding the reactor core, a downcomer region disposed between an inner surface of the reactor pressure vessel and the core shroud, a steam line connected to an upper end of the reactor pressure vessel and a condenser system that receives steam from the reactor pressure vessel. A portion of the condenser system condensate is returned to the reactor pressure vessel of the boiling water reactor inside the core barrel above the core rather than into the downcomer. Returning the condensate in this way increases the effectiveness of an isolation condenser system or if the condensate is a portion of the feedwater from the main condenser it provides an effective means to regulate core flow and core power.
G21C 15/12 - Arrangement or disposition of passages in which heat is transferred to the coolant, e.g. for coolant circulation through the supports of the fuel elements from containment vessel
G21C 1/08 - Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling-water reactor, integral-superheat reactor, pressurised-water reactor
G21C 7/32 - Control of nuclear reaction by varying flow of coolant through the core
A fuel movement simulator system includes a virtual reality (VR) system configured to generate a virtual refuel floor environment; and a fuel movement simulator assembly configured to provide a physical interface to the virtual refuel floor environment, the fuel movement simulator assembly including a replica mast, a replica control console connected to the replica mast, and a support structure configured to support the replica mast and replica control console.
G06F 3/00 - Input arrangements for transferring data to be processed into a form capable of being handled by the computer; Output arrangements for transferring data from processing unit to output unit, e.g. interface arrangements
G06T 19/00 - Manipulating 3D models or images for computer graphics
G09B 9/00 - Simulators for teaching or training purposes
G21C 19/20 - Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
A fuel movement simulator system includes a virtual reality (VR) system configured to generate a virtual refuel floor environment; and a fuel movement simulator assembly configured to provide a physical interface to the virtual refuel floor environment, the fuel movement simulator assembly including a replica mast, a replica control console connected to the replica mast, and a support structure configured to support the replica mast and replica control console.
G06F 3/00 - Input arrangements for transferring data to be processed into a form capable of being handled by the computer; Output arrangements for transferring data from processing unit to output unit, e.g. interface arrangements
G06T 19/00 - Manipulating 3D models or images for computer graphics
G09B 9/00 - Simulators for teaching or training purposes
G21C 19/20 - Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
A fuel movement simulator system includes a virtual reality (VR) system configured to generate a virtual refuel floor environment; and a fuel movement simulator assembly configured to provide a physical interface to the virtual refuel floor environment, the fuel movement simulator assembly including a replica mast, a replica control console connected to the replica mast, and a support structure configured to support the replica mast and replica control console.
Damper systems selectively reduce coolant fluid flow in nuclear reactor passive cooling systems, including related RVACS. Systems include a damper that blocks the flow in a coolant conduit and is moveable to open, closed, and intermediate positions. The damper blocks the coolant flow when closed to prevent heat loss, vibration, and development of large temperature gradients, and the damper passively opens, to allow full coolant flow, at failure and in transient scenarios. The damper may be moveable by an attachment extending into the coolant channel that holds the damper in a closed position. When a transient occurs, the resulting loss of power and/or overheat causes the attachment to stop holding the damper, which may be driven by gravity, pressure, a spring, or other passive structure into the open position for full coolant flow. A power source and temperature-dependent switch may detect and stop holding the damper closed in such scenarios.
G21C 15/02 - Arrangement or disposition of passages in which heat is transferred to the coolant, e.g. for coolant circulation through the supports of the fuel elements
The method includes configuring a nuclear reactor to at least partially mitigate liquid metal coolant backflow in the nuclear reactor in response to an at least partial failure of a primary electromagnetic pump (EMP) within a reactor pressure vessel of the nuclear reactor, the nuclear reactor being liquid metal-cooled, the primary EMP configured to circulate liquid metal coolant through at least a reactor core of the nuclear reactor, the configuring including, installing a backflow EMP within the reactor pressure vessel, such that when selectively activated, the backflow EMP at least partially mitigates liquid metal coolant backflow through the primary EMP.
Casks shield materials and passively remove heat via heat transport paths from deep inside to outside the cask. The transport path may be heat pipes and conductive rods that are non-linear so that radiation is always shielded by the cask. A damper may surround an end of the heat transport path to control heat loss from the cask. A jacket of fluid or meltable material that conducts heat by convection may surround stored materials ensure an even temperature within the cask, and the heat transport path may absorb heat from the jacket. Casks are useable to safely store, transport, and dispose of any sensitive or heat-generating material. Casks may be opened or closed to simultaneously load and offload materials at a consistent operating temperature provided by heaters in the cask.
Control rod drives include linearly-moveable control elements inside an isolation barrier. Control rod drives move the control element through secured magnetic elements subject to magnetic fields. Induction coils may generate magnetic fields and be moveable across a full stroke length of the control element in the reactor. A motor may spin a linear screw to move the induction coils on a vertical travel nut. A control rod assembly may house the magnetic elements and directly, removably join to the control element. The control rod assembly may lock with magnetic overtravel latches inside the isolation barrier to maintain an overtravel position. Overtravel release coils outside the isolation barrier may release the latches to leave the overtravel position. Operation includes moving the induction coils with a linear screw to drive the control element to desired insertion points, including full insertion by gravity following de-energization. No direct connection may penetrate the isolation barrier.
A boiling water reactor includes a reactor building, a reactor cavity pool, a primary containment vessel, and a passive containment cooling system. The reactor building includes a top wall defining a penetration therein, a bottom wall, and at least one side wall, which define a chamber. At least a portion of the primary containment vessel is in the chamber. The passive containment cooling system includes a thermal exchange pipe including an outer pipe and an inner pipe. The outer pipe has a first outer pipe end and a second outer pipe end. The first outer pipe end is closed and in the primary containment vessel. The second outer pipe end is open and extends into the reactor cavity pool. The inner pipe has a first inner pipe end and a second inner pipe end, which are open. The second inner pipe end extends out of the outer pipe and into the reactor cavity pool.
A boiling water reactor system includes a reactor vessel including a reactor core. A steam line is in communication with the reactor core and a turbine that is connected to an electrical generator. A dry standby liquid control system includes a standby vessel containing dry powder containing boron and including a high pressure water supply in communication with the standby vessel via a first closed valve, wherein the standby vessel is in communication with the reactor vessel via a second closed valve.
G21C 9/033 - Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse by an absorbent fluid
G21C 7/22 - Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of a fluid or fluent neutron-absorbing material
A boiling water reactor system includes a reactor vessel including a reactor core. A steam line is in communication with the reactor core and a turbine that is connected to an electrical generator. A dry standby liquid control system includes a standby vessel containing dry powder containing boron and including a high pressure water supply in communication with the standby vessel via a first closed valve, wherein the standby vessel is in communication with the reactor vessel via a second closed valve.
G21C 7/22 - Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of a fluid or fluent neutron-absorbing material
G21C 9/033 - Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse by an absorbent fluid
A boiling water reactor includes a reactor building, a reactor cavity pool, a primary containment vessel, and a passive containment cooling system. The reactor building includes a top wall defining a penetration therein, a bottom wall, and at least one side wall, which define a chamber. At least a portion of the primary containment vessel is in the chamber. The passive containment cooling system includes a thermal exchange pipe including an outer pipe and an inner pipe. The outer pipe has a first outer pipe end and a second outer pipe end. The first outer pipe end is closed and in the primary containment vessel. The second outer pipe end is open and extends into the reactor cavity pool. The inner pipe has a first inner pipe end and a second inner pipe end, which are open. The second inner pipe end extends out of the outer pipe and into the reactor cavity pool.
Various example embodiments are directed towards an improved control drum, as well as systems, apparatuses, and/or methods for operating a nuclear reactor with a plurality of improved control drums. The control drum includes an outer shell, an inner shell, a plurality of tubes, the plurality of tubes including at least one neutron absorbing tube and at least one neutron scattering tube, and at least one baffle plate arranged between the outer shell and the inner shell, the at least one baffle plate including a plurality of perforations, and at least one perforation of the plurality of perforations configured to support a tube of the plurality of tubes.
Various example embodiments are directed towards an improved control drum, as well as systems, apparatuses, and/or methods for operating a nuclear reactor with a plurality of improved control drums. The control drum includes an outer shell, an inner shell, a plurality of tubes, the plurality of tubes including at least one neutron absorbing tube and at least one neutron scattering tube, and at least one baffle plate arranged between the outer shell and the inner shell, the at least one baffle plate including a plurality of perforations, and at least one perforation of the plurality of perforations configured to support a tube of the plurality of tubes.
A nuclear plant includes a nuclear reactor, a containment structure that at least partially defines a containment environment of the nuclear reactor, and a passive containment cooling system that causes coolant fluid to flow downwards from a coolant reservoir to a bottom of a coolant channel coupled to the containment structure and rise through the coolant channel toward the coolant reservoir due to absorbing heat from the nuclear reactor. A check valve assembly, in fluid communication with the coolant reservoir, selectively enables one-way flow of a containment fluid from the containment environment to the coolant reservoir, based on a pressure at an inlet being equal to or greater than a threshold magnitude. A fusible plug, in fluid communication with the coolant reservoir at a bottom vertical depth below the bottom of the coolant reservoir, enables coolant fluid to flow into the containment structure based on at least partially melting.
G21C 15/12 - Arrangement or disposition of passages in which heat is transferred to the coolant, e.g. for coolant circulation through the supports of the fuel elements from containment vessel
Various example embodiments are directed towards an improved control drum, as well as systems, apparatuses, and/or methods for operating a nuclear reactor with a plurality of improved control drums. The control drum includes an outer shell, an inner shell, a plurality of tubes, the plurality of tubes including at least one neutron absorbing tube and at least one neutron scattering tube, and at least one baffle plate arranged between the outer shell and the inner shell, the at least one baffle plate including a plurality of perforations, and at least one perforation of the plurality of perforations configured to support a tube of the plurality of tubes.
G21C 7/08 - Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
G21C 7/103 - Control assemblies containing one or more absorbants as well as other elements, e.g. fuel or moderator elements
G21C 7/28 - Control of nuclear reaction by displacement of the reflector or parts thereof
A nuclear plant includes a nuclear reactor, a containment structure that at least partially defines a containment environment of the nuclear reactor, and a passive containment cooling system that causes coolant fluid to flow downwards from a coolant reservoir to a bottom of a coolant channel coupled to the containment structure and rise through the coolant channel toward the coolant reservoir due to absorbing heat from the nuclear reactor. A check valve assembly, in fluid communication with the coolant reservoir, selectively enables one-way flow of a containment fluid from the containment environment to the coolant reservoir, based on a pressure at an inlet being equal to or greater than a threshold magnitude. A fusible plug, in fluid communication with the coolant reservoir at a bottom vertical depth below the bottom of the coolant reservoir, enables coolant fluid to flow into the containment structure based on at least partially melting.
G21C 15/12 - Arrangement or disposition of passages in which heat is transferred to the coolant, e.g. for coolant circulation through the supports of the fuel elements from containment vessel
71.
Dry stand-by liquid control system for a nuclear reactor
A boiling water reactor system includes a reactor vessel including a reactor core. A steam line is in communication with the reactor core and a turbine that is connected to an electrical generator. A dry standby liquid control system includes a standby vessel containing dry powder containing boron and including a high pressure water supply in communication with the standby vessel via a first closed valve, wherein the standby vessel is in communication with the reactor vessel via a second closed valve.
G21C 9/033 - Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse by an absorbent fluid
G21C 9/02 - Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse
G21C 1/08 - Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling-water reactor, integral-superheat reactor, pressurised-water reactor
G21C 15/16 - Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants comprising means for separating liquid and steam
G21C 13/02 - Pressure vessels; Containment vessels; Containment in general - Details
G21C 7/22 - Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of a fluid or fluent neutron-absorbing material
72.
Passive containment cooling system for boiling water reactor and method of installation
A boiling water reactor includes a reactor building, a reactor cavity pool, a primary containment vessel, and a passive containment cooling system. The reactor building includes a top wall defining a penetration therein, a bottom wall, and at least one side wall, which define a chamber. At least a portion of the primary containment vessel is in the chamber. The passive containment cooling system includes a thermal exchange pipe including an outer pipe and an inner pipe. The outer pipe has a first outer pipe end and a second outer pipe end. The first outer pipe end is closed and in the primary containment vessel. The second outer pipe end is open and extends into the reactor cavity pool. The inner pipe has a first inner pipe end and a second inner pipe end, which are open. The second inner pipe end extends into the reactor cavity pool.
G21C 15/16 - Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants comprising means for separating liquid and steam
G21C 1/08 - Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling-water reactor, integral-superheat reactor, pressurised-water reactor
G21C 19/303 - Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products specially adapted for gases
G21C 21/00 - Apparatus or processes specially adapted to the manufacture of reactors or parts thereof
73.
INTEGRATED PASSIVE COOLING CONTAINMENT STRUCTURE FOR A NUCLEAR REACTOR
An integrated passive cooling containment structure for a nuclear reactor includes a concentric arrangement of an inner steel cylindrical shell and an outer steel cylindrical shell that define both a lateral boundary of a containment environment of the nuclear reactor that is configured to accommodate a nuclear reactor and an annular gap space between the inner and outer steel cylindrical shells, a concrete donut structure at a bottom of the annular gap space, and a plurality of concrete columns spaced apart azimuthally around a circumference of the annular gap and extending in parallel from a top surface of the concrete donut structure to a top of the annular gap space. The outer and inner steel cylindrical shells and the concrete donut structure at least partially define one or more coolant channels extending through the annular gap space.
G21C 15/12 - Arrangement or disposition of passages in which heat is transferred to the coolant, e.g. for coolant circulation through the supports of the fuel elements from containment vessel
A nuclear plant includes a nuclear reactor, a containment structure that at least partially defines a containment environment of the nuclear reactor, and a passive containment cooling system that causes coolant fluid to flow downwards from a coolant reservoir to a bottom of a coolant channel coupled to the containment structure and rise through the coolant channel toward the coolant reservoir due to absorbing heat from the nuclear reactor. A check valve assembly, in fluid communication with the coolant reservoir, selectively enables one-way flow of a containment fluid from the containment environment to the coolant reservoir, based on a pressure at an inlet being equal to or greater than a threshold magnitude. A fusible plug, in fluid communication with the coolant reservoir at a bottom vertical depth below the bottom of the coolant reservoir, enables coolant fluid to flow into the containment structure based on at least partially melting.
F16K 17/38 - Safety valves; Equalising valves actuated in consequence of extraneous circumstances, e.g. shock, change of position of excessive temperature
G21C 9/02 - Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse
G21C 9/033 - Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse by an absorbent fluid
G21C 15/20 - Partitions or thermal insulation between fuel channel and moderator, e.g. in pressure tube reactors
75.
Integrated passive cooling containment structure for a nuclear reactor
An integrated passive cooling containment structure for a nuclear reactor includes a concentric arrangement of an inner steel cylindrical shell and an outer steel cylindrical shell that define both a lateral boundary of a containment environment of the nuclear reactor that is configured to accommodate a nuclear reactor and an annular gap space between the inner and outer steel cylindrical shells, a concrete donut structure at a bottom of the annular gap space, and a plurality of concrete columns spaced apart azimuthally around a circumference of the annular gap and extending in parallel from a top surface of the concrete donut structure to a top of the annular gap space. The outer and inner steel cylindrical shells and the concrete donut structure at least partially define one or more coolant channels extending through the annular gap space.
G21C 13/10 - Means for preventing contamination in event of leakage
G21C 15/12 - Arrangement or disposition of passages in which heat is transferred to the coolant, e.g. for coolant circulation through the supports of the fuel elements from containment vessel
E04H 7/18 - Containers for fluids or gases; Supports therefor mainly of concrete, e.g. reinforced concrete, or other stone-like material
G21C 13/028 - Seals, e.g. for pressure vessels or containment vessels
Casks (100) shield materials and passively remove heat via heat transport paths (150) from deep inside to outside the cask. The transport path may be heat pipes and conductive rods that are non-linear so that radiation is always shielded by the cask. A damper (160) may surround an end of the heat transport path to control heat loss from the cask. A jacket (110) of fluid or meltable material that conducts heat by convection may surround stored materials ensure an even temperature within the cask, and the heat transport path may absorb heat from the jacket. Casks are useable to safely store, transport, and dispose of any sensitive or heat-generating material. Casks may be opened or closed to simultaneously load and offload materials at a consistent operating temperature provided by heaters in the cask.
G21F 5/14 - Devices for handling containers or shipping-casks, e.g. transporting devices
G21C 19/32 - Apparatus for removing radioactive objects or materials from the reactor discharge area, e.g. to a storage place; Apparatus for handling radioactive objects or materials within a storage place or removing them therefrom
77.
PASSIVE HEAT REMOVAL CASKS AND METHODS OF USING THE SAME
Casks (100) shield materials and passively remove heat via heat transport paths (150) from deep inside to outside the cask. The transport path may be heat pipes and conductive rods that are non-linear so that radiation is always shielded by the cask. A damper (160) may surround an end of the heat transport path to control heat loss from the cask. A jacket (110) of fluid or meltable material that conducts heat by convection may surround stored materials ensure an even temperature within the cask, and the heat transport path may absorb heat from the jacket. Casks are useable to safely store, transport, and dispose of any sensitive or heat-generating material. Casks may be opened or closed to simultaneously load and offload materials at a consistent operating temperature provided by heaters in the cask.
G21F 5/14 - Devices for handling containers or shipping-casks, e.g. transporting devices
G21C 19/32 - Apparatus for removing radioactive objects or materials from the reactor discharge area, e.g. to a storage place; Apparatus for handling radioactive objects or materials within a storage place or removing them therefrom
78.
Method for inspecting core shroud using remote operated vehicle (ROV)
The method includes installing a system for inspecting the core shroud on the core shroud, driving the system horizontally around the core shroud, and using a sensor of the system to inspect the core shroud, where the system includes a trolley, an arm, a tether, and a remotely operated vehicle (ROV) for inspecting the core shroud. The ROV includes a body configured to be operatively connected to the tether, and the sensor is configured to be operatively connected to the body, and configured to provide inspection information of the core shroud. The arm is configured to be operatively connected to the trolley. The ROV is configured to be operatively connected to the arm via the tether, and the tether is configured to provide vertical position information for the ROV relative to the outer surface of the core shroud.
G21C 19/20 - Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
G21C 17/01 - Inspection of the inner surfaces of vessels
G21C 17/007 - Inspection of the outer surfaces of vessels
G01N 29/265 - Arrangements for orientation or scanning by moving the sensor relative to a stationary material
B25J 11/00 - Manipulators not otherwise provided for
F22B 37/48 - Devices or arrangements for removing water, minerals, or sludge from boilers
F22B 37/00 - Component parts or details of steam boilers
79.
Digital systems and methods for high precision control in nuclear reactors
Control rod drives include all-digital monitoring, powering, and controlling systems for operating the drives. Each controlling system includes distinct microprocessor-driven channels that independently monitor and handle control rod drive position information reported from multiple position sensors per drive. Controlling systems function as rod control and information systems with top-level hardware interfaced with nuclear plant operators other plant systems. The top-level hardware can receive operator instructions and report control rod position, as well as report errors detected using redundant data from the multiple sensors. Positional data received from each drive is multiplexed across plural, redundant channels to allow verification of the system using independent position data as well as operation of the system should a single channel or detector fail. Control rod drives are capable of positioning and detecting position of control elements in fine increments, such as 3-millimeter increments, with plural position sensors that digitally report drive status and position.
Combined cleanup and heat sink systems work with nuclear reactor coolant loops. Combined systems may join hotter and colder sections of the coolant loops in parallel with any steam generator or other extractor and provide optional heat removal between the same. Combined systems also remove impurities or debris from a fluid coolant without significant heat loss from the coolant. A cooler in the combined system may increase in capacity or be augmented in number to move between purifying cooling and major heat removal from the coolant, potentially as an emergency cooler. The cooler may be joined to the hotter and colder sections through valved flow paths depending on desired functionality. Sections of the coolant loops may be fully above the cooler, which may be above the reactor, to drive flow by gravity and enhance isolation of sections of the coolant loop.
G21C 15/02 - Arrangement or disposition of passages in which heat is transferred to the coolant, e.g. for coolant circulation through the supports of the fuel elements
81.
COOLANT CLEANUP AND HEAT-SINKING SYSTEMS AND METHODS OF OPERATING THE SAME
Combined cleanup and heat sink systems work with nuclear reactor coolant loops. Combined systems may join hotter and colder sections of the coolant loops in parallel with any steam generator or other extractor and provide optional heat removal between the same. Combined systems also remove impurities or debris from a fluid coolant without significant heat loss from the coolant. A cooler in the combined system may increase in capacity or be augmented in number to move between purifying cooling and major heat removal from the coolant, potentially as an emergency cooler. The cooler may be joined to the hotter and colder sections through valved flow paths depending on desired functionality. Sections of the coolant loops may be fully above the cooler, which may be above the reactor, to drive flow by gravity and enhance isolation of sections of the coolant loop.
G21C 15/02 - Arrangement or disposition of passages in which heat is transferred to the coolant, e.g. for coolant circulation through the supports of the fuel elements
82.
Coolant cleanup and heat-sinking systems and methods of operating the same
Combined cleanup and heat sink systems work with nuclear reactor coolant loops. Combined systems may join hotter and colder sections of the coolant loops in parallel with any steam generator or other extractor and provide optional heat removal between the same. Combined systems also remove impurities or debris from a fluid coolant without significant heat loss from the coolant. A cooler in the combined system may increase in capacity or be augmented in number to move between purifying cooling and major heat removal from the coolant, potentially as an emergency cooler. The cooler may be joined to the hotter and colder sections through valved flow paths depending on desired functionality. Sections of the coolant loops may be fully above the cooler, which may be above the reactor, to drive flow by gravity and enhance isolation of sections of the coolant loop.
G21C 19/307 - Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products specially adapted for liquids
Nuclear reactors include isolation condenser systems that can be selectively connected with the reactor to provide desired cooling and pressure relief. Isolation condensers are immersed in a separate chamber holding coolant to which the condenser can transfer heat from the nuclear reactor. The chamber may selectively connect to an adjacent coolant reservoir for multiple isolation condensers. A check valve may permit coolant to flow only from the reservoir to the isolation condenser. A passive switch can operate the check valve and other isolating components. Isolation condensers can be activated by opening an inlet and outlet to/from the reactor for coolant flow. Fluidic controls and/or a pressure pulse transmitter may monitor reactor conditions and selectively activate individual isolation condensers by opening such flows. Isolation condenser systems may be positioned outside of containment in an underground silo with the containment, which may not have any other coolant source.
G21C 15/16 - Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants comprising means for separating liquid and steam
G21C 15/02 - Arrangement or disposition of passages in which heat is transferred to the coolant, e.g. for coolant circulation through the supports of the fuel elements
Pressure vessels have full penetrations that can be opened and closed with no separate valve piping or external valve. A projected volume from the vessel wall may house valve structures and flow path, and these structures may move with an external actuator. The flow path may extend both along and into the projected volume. Vessel walls may remain a minimum thickness even at the penetration, and any type of gates may be used with any degree of duplication. Penetrations may be formed by installing valve gates directly into the channel in the wall. The wall may be built outward into the projected volume by forging or welding additional pieces integrally machining the channel through the same volume and wall. Additional passages for gates and actuators may be machined into the projections as well. Pressure vessels may not require flanges at join points or material seams for penetration flow paths.
G21C 13/02 - Pressure vessels; Containment vessels; Containment in general - Details
G21C 9/00 - Emergency protection arrangements structurally associated with the reactor
G21C 15/02 - Arrangement or disposition of passages in which heat is transferred to the coolant, e.g. for coolant circulation through the supports of the fuel elements
Pressure vessels have full penetrations that can be opened and closed with no separate valve piping or external valve. A projected volume from the vessel wall may house valve structures and flow path, and these structures may move with an external actuator. The flow path may extend both along and into the projected volume. Vessel walls may remain a minimum thickness even at the penetration, and any type of gates may be used with any degree of duplication. Penetrations may be formed by installing valve gates directly into the channel in the wall. The wall may be built outward into the projected volume by forging or welding additional pieces integrally machining the channel through the same volume and wall. Additional passages for gates and actuators may be machined into the projections as well. Pressure vessels may not require flanges at join points or material seams for penetration flow paths.
G21C 1/08 - Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling-water reactor, integral-superheat reactor, pressurised-water reactor
86.
Method of cleaning a throat section of a jet pump assembly of a nuclear reactor
A method of cleaning a jet pump assembly of a nuclear reactor may comprise inserting a cleaning tool into the jet pump assembly such that a front face of the cleaning tool is adjacent to an inner surface of the jet pump assembly and below a level of a first liquid in the jet pump assembly. The method may additionally comprise directing a plurality of front jets of a second liquid from a plurality of front orifices on the front face of the cleaning tool such that the plurality of front jets of the second liquid strikes the inner surface of the jet pump assembly. The method may further comprise maintaining a standoff distance between the front face of the cleaning tool and the inner surface of the jet pump assembly during the cleaning of the jet pump assembly.
B08B 9/032 - Cleaning the internal surfaces; Removal of blockages by the mechanical action of a moving fluid, e.g. by flushing
B08B 9/043 - Cleaning the internal surfaces; Removal of blockages using cleaning devices introduced into and moved along the pipes moved by externally powered mechanical linkage, e.g. pushed or drawn through the pipes
B05B 1/16 - Nozzles, spray heads or other outlets, with or without auxiliary devices such as valves, heating means with strainers in or outside the outlet opening having selectively-effective outlets
G21C 15/25 - Promoting flow of the coolant for liquids using jet pumps
B05B 13/06 - Machines or plants for applying liquids or other fluent materials to surfaces of objects or other work by spraying, not covered by groups specially designed for treating the inside of hollow bodies
B05B 15/652 - Mounting arrangements for fluid connection of the spraying apparatus or its outlets to flow conduits whereby the jet can be oriented
B05B 12/16 - Arrangements for controlling delivery; Arrangements for controlling the spray area for controlling the spray area
G21C 17/017 - Inspection or maintenance of pipe-lines or tubes in nuclear installations
B08B 9/047 - Cleaning the internal surfaces; Removal of blockages using cleaning devices introduced into and moved along the pipes moved by externally powered mechanical linkage, e.g. pushed or drawn through the pipes the cleaning devices having motors for powering cleaning tools
87.
INTEGRAL PRESSURE VESSEL PENETRATIONS AND SYSTEMS AND METHODS FOR USING AND FABRICATING THE SAME
Pressure vessels have full penetrations that can be opened and closed with no separate valve piping or external valve. A projected volume from the vessel wall may house valve structures and flow path, and these structures may move with an external actuator. The flow path may extend both along and into the projected volume. Vessel walls may remain a minimum thickness even at the penetration, and any type of gates may be used with any degree of duplication. Penetrations may be formed by installing valve gates directly into the channel in the wall. The wall may be built outward into the projected volume by forging or welding additional pieces integrally machining the channel through the same volume and wall. Additional passages for gates and actuators may be machined into the projections as well. Pressure vessels may not require flanges at join points or material seams for penetration flow paths.
G21C 9/00 - Emergency protection arrangements structurally associated with the reactor
G21C 15/02 - Arrangement or disposition of passages in which heat is transferred to the coolant, e.g. for coolant circulation through the supports of the fuel elements
88.
Magnetically-actuated isolated rod couplings for use in a nuclear reactor control rod drive
Control rod drives include linearly-moveable control elements inside an isolation barrier. Control rod drives move the control element through a motor and rotor powering a linear screw internal to an isolation barrier. Induction coils may generate magnetic fields and be moveable across a full stroke length of the control element in the reactor. The magnetic fields hold closed a releasable latch to disconnect the control elements from the linear drives. A control rod assembly may join to the control element. The control rod assembly may lock with magnetic overtravel latches inside the isolation barrier to maintain an overtravel position. Overtravel release coils outside the isolation barrier may release the latches to leave the overtravel position. Operation includes moving the magnetic fields and releasable latch together on opposite sides of an isolation barrier to drive the control element to desired insertion points, including full insertion by gravity following de-energization.
A system for measuring a level of a liquid may include a receptacle, a probe, a pulsing unit, and a digitizer. The receptacle has a top and a bottom and is configured to contain the liquid. The probe may extend into the receptacle through the bottom. The pulsing unit is configured to transmit a pulse to the probe. The digitizer is configured to receive at least a first reflected pulse and a second reflected pulse from the probe. The time between the first reflected pulse and the second reflected pulse may be calculated and converted to a distance that is indicative of the level of the liquid in the receptacle.
A combined blade guide and exchange tool, include a blade guide tool having a lower end and an upper end and a plurality of frame rails supporting a pair of lower collet housings at a lower end of the blade guide tool. A pair of fuel support grapple actuating rods are supported between the plurality of frame rails and have a first end engaging a pair of collets within the pair of lower collet housings and a second end disposed at the upper end of the blade guide tool. A blade exchange tool is releasably mounted to the upper end of the blade guide tool and includes a pair of upper collets for engaging the pair of fuel support grapple actuating rods. The blade exchange tool further including a slider and hook assembly attached to a cable guided by the blade exchange tool and adapted for engaging a control rod.
G21C 19/10 - Lifting devices or pulling devices adapted for co-operation with fuel elements or with control elements
G21C 19/20 - Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
91.
BOILING WATER REACTOR BLADE GUIDE AND EXCHANGE TOOL
A combined blade guide and exchange tool, include a blade guide tool (12) having a lower end and an upper end and a plurality of frame rails (34a, 34b, 36a, 36b) supporting a pair of lower collet housings (30) at a lower end of the blade guide tool (12). A pair of fuel support grapple actuating rods (44) are supported between the plurality of frame rails (34a, 34b, 36a, 36b) and have a first end engaging a pair of collets (32) within the pair of lower collet housings (30) and a second end disposed at the upper end of the blade guide tool (12). A blade exchange tool (14) is releasably mounted to the upper end of the blade guide tool (12) and includes a pair of upper collets (90) for engaging the pair of fuel support grapple actuating rods (44). The blade exchange tool (14) further including a slider (80) and hook (82) assembly attached to a cable (76) guided by the blade exchange tool and adapted for engaging a control rod (20).
G21C 19/10 - Lifting devices or pulling devices adapted for co-operation with fuel elements or with control elements
G21C 19/20 - Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
92.
BOILING WATER REACTOR BLADE GUIDE AND EXCHANGE TOOL
A combined blade guide and exchange tool, includes a blade guide tool having lower and upper ends and a plurality of frame rails supporting a pair of lower collet housings at a lower end of the blade guide tool. A pair of fuel support grapple actuating rods are supported between the plurality of frame rails and have a first end engaging a pair of collets within the pair of lower collet housings and a second end disposed at the upper end of the blade guide tool. A blade exchange tool is releasably mounted to the upper end of the blade guide tool and includes a pair of upper collets for engaging the pair of fuel support grapple actuating rods. The blade exchange tool further includes a slider and hook assembly attached to a cable guided by the blade exchange tool and adapted for engaging a control rod.
G21C 19/10 - Lifting devices or pulling devices adapted for co-operation with fuel elements or with control elements
G21C 19/20 - Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
A feedwater sparger repair assembly includes a cover plate having a partial cylindrical shape and having a nozzle opening and a pair of bolt openings extending through the cover plate. A nozzle is attached to the cover plate and surrounds the nozzle opening. A pair of T-bolts extend through a respective one of the pair of bolt openings and each include a shank having a threaded portion extending from an exterior side of the cover plate and a partial cylindrical head portion disposed at an end of the shank on an interior side of the cover plate. A pair of nuts are engaged with the threaded portion of the pair of T-bolts. The feedwater sparger repair assembly is adapted to be mounted to an opening that is cut into a core spray pipe in order to repair/replace a sparger that becomes cracked.
G21C 17/017 - Inspection or maintenance of pipe-lines or tubes in nuclear installations
F16L 55/18 - Appliances for use in repairing pipes
F16L 41/06 - Tapping pipe walls, i.e. making connections through the walls of pipes while they are carrying fluids; Fittings therefor making use of attaching means embracing the pipe
F16L 55/179 - Devices for covering leaks in pipes or hoses, e.g. hose-menders specially adapted for bends, branch units, branching pipes or the like
94.
USE OF ISOLATION CONDENSER AND/OR FEEDWATER TO LIMIT CORE FLOW, CORE POWER, AND PRESSURE IN A BOILING WATER REACTOR
A method and apparatus of limiting power of a boiling water nuclear reactor system includes a reactor pressure vessel, a reactor core disposed in the reactor pressure vessel, a core shroud surrounding the reactor core, a downcomer region disposed between an inner surface of the reactor pressure vessel and the core shroud, a steam line connected to an upper end of the reactor pressure vessel and a condenser system that receives steam from the reactor pressure vessel. A portion of the condenser system condensate is returned to the reactor pressure vessel of the boiling water reactor inside the core barrel above the core rather than into the downcomer. Returning the condensate in this way increases the effectiveness of an isolation condenser system or if the condensate is a portion of the feedwater from the main condenser it provides an effective means to regulate core flow and core power.
G21C 1/08 - Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling-water reactor, integral-superheat reactor, pressurised-water reactor
G21C 7/32 - Control of nuclear reaction by varying flow of coolant through the core
A method and apparatus of limiting power of a boiling water nuclear reactor system includes a reactor pressure vessel, a reactor core disposed in the reactor pressure vessel, a core shroud surrounding the reactor core, a downcomer region disposed between an inner surface of the reactor pressure vessel and the core shroud, a steam line connected to an upper end of the reactor pressure vessel and a condenser system that receives steam from the reactor pressure vessel. A portion of the condenser system condensate is returned to the reactor pressure vessel of the boiling water reactor inside the core barrel above the core rather than into the downcomer. Returning the condensate in this way increases the effectiveness of an isolation condenser system or if the condensate is a portion of the feedwater from the main condenser it provides an effective means to regulate core flow and core power.
G21C 1/08 - Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling-water reactor, integral-superheat reactor, pressurised-water reactor
G21C 7/32 - Control of nuclear reaction by varying flow of coolant through the core
A method and apparatus of limiting power of a boiling water nuclear reactor system includes a reactor pressure vessel, a reactor core disposed in the reactor pressure vessel, a core shroud surrounding the reactor core, a downcomer region disposed between an inner surface of the reactor pressure vessel and the core shroud, a steam line connected to an upper end of the reactor pressure vessel and a condenser system that receives steam from the reactor pressure vessel. A portion of the condenser system condensate is returned to the reactor pressure vessel of the boiling water reactor inside the core barrel above the core rather than into the downcomer. Returning the condensate in this way increases the effectiveness of an isolation condenser system or if the condensate is a portion of the feedwater from the main condenser it provides an effective means to regulate core flow and core power.
G21C 1/08 - Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling-water reactor, integral-superheat reactor, pressurised-water reactor
G21C 15/12 - Arrangement or disposition of passages in which heat is transferred to the coolant, e.g. for coolant circulation through the supports of the fuel elements from containment vessel
G21D 5/06 - Reactor and engine not structurally combined with engine working medium circulating through reactor core
G21C 15/25 - Promoting flow of the coolant for liquids using jet pumps
97.
Systems and methods for steam reheat in power plants
Steam generators in power plants exchange energy from a primary medium to a secondary medium for energy extraction. Steam generators include one or more primary conduits and one or more secondary conduits. The conduits do not intermix the mediums and may thus discriminate among different fluid sources and destinations. One conduit may boil feedwater while another reheats steam for use in lower and higher-pressure turbines, respectively. Valves and other selectors divert steam and/or water into the steam generator or to other turbines or the environment for load balancing and other operational characteristics. Conduits circulate around an interior perimeter of the steam generator immersed in the primary medium and may have different cross-sections, radii, and internal structures depending on contained. A water conduit may have less flow area and a tighter coil radius. A steam conduit may include a swirler and rivulet stopper to intermix water in any steam flow.
F01K 7/38 - Steam engine plants characterised by the use of specific types of engine; Plants or engines characterised by their use of special steam systems, cycles or processes; Control means specially adapted for such systems, cycles or processes; Use of withdrawn or exhaust steam for feed-water heating the engines being of extraction or non-condensing type; Use of steam for feed-water heating the engines being of turbine type
G21D 5/16 - Liquid working medium vaporised by reactor coolant superheated by separate heat source
F22B 1/02 - Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers
F01K 19/00 - Regenerating or otherwise treating steam exhaust from steam engine plant
F01K 7/34 - Steam engine plants characterised by the use of specific types of engine; Plants or engines characterised by their use of special steam systems, cycles or processes; Control means specially adapted for such systems, cycles or processes; Use of withdrawn or exhaust steam for feed-water heating the engines being of extraction or non-condensing type; Use of steam for feed-water heating
F01K 7/44 - Use of steam for feed-water heating and another purpose
F01K 11/02 - Steam engine plants characterised by the engines being structurally combined with boilers or condensers the engines being turbines
G21D 5/12 - Liquid working medium vaporised by reactor coolant
G21D 1/00 - NUCLEAR POWER PLANT - Details of nuclear power plant
A feedwater sparger repair assembly includes a cover plate having a partial cylindrical shape and having a nozzle opening and a pair of bolt openings extending through the cover plate. A nozzle is attached to the cover plate and surrounds the nozzle opening. A pair of T-bolts extend through a respective one of the pair of bolt openings and each include a shank having a threaded portion extending from an exterior side of the cover plate and a partial cylindrical head portion disposed at an end of the shank on an interior side of the cover plate. A pair of nuts are engaged with the threaded portion of the pair of T-bolts. The feedwater sparger repair assembly is adapted to be mounted to an opening that is cut into a core spray pipe in order to repair/replace a sparger that becomes cracked.
Nuclear reactors have very few systems for significantly reduced failure possibilities. Nuclear reactors may be boiling water reactors with natural circulation-enabling heights and smaller, flexible energy outputs in the 0-350 megawatt-electric range. Reactors are fully surrounded by an impermeable, high-pressure containment. No coolant pools, heat sinks, active pumps, or other emergency fluid sources may be present inside containment; emergency cooling, like isolation condenser systems, are outside containment. Isolation valves integral with the reactor pressure vessel provide working and emergency fluid through containment to the reactor. Isolation valves are one-piece, welded, or otherwise integral with reactors and fluid conduits having ASME-compliance to eliminate risk of shear failure. Containment may be completely underground and seismically insulated to minimize footprint and above-ground target area.
G21C 13/036 - Joints between tubes and vessel walls, e.g. taking into account thermal stresses the tube passing through the vessel wall, i.e. continuing on both sides of the wall
G21C 1/08 - Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling-water reactor, integral-superheat reactor, pressurised-water reactor
G21C 1/02 - Fast fission reactors, i.e. reactors not using a moderator
Systems remotely polish and compress surfaces for working, including surfaces created through electrical discharge machining. A bridge may secure about the surface and carry a spindle that rotatably extends downward and carries a polishing assembly. The polishing assembly can push against the surface while polishing the same with larger amounts of force. The polisher can be moved about a perimeter of the surface and vertically. Systems may be remotely operated with a pneumatic slide, hydraulic motor, and/or stepper motor. Spotfaces formed from electrical discharge machining, including those in nuclear facilities and deep underwater, may have recast layers removed with such systems without manual or direct operator interface.
B24B 29/02 - Machines or devices for polishing surfaces on work by means of tools made of soft or flexible material with or without the application of solid or liquid polishing agents designed for particular workpieces
B24B 47/22 - Equipment for exact control of the position of the grinding tool or work at the start of the grinding operation
patents
