A system comprising a reactor pressure vessel (RPV), a flange attached to the RPV, a welded seal connecting the flange to the RPV, a compression seal at least partially disposed within the flange, and a cover plate including a first portion engaged with the flange, and a second portion engaged with the RPV via one or more fasteners.
G21C 19/04 - Means for controlling flow of coolant over objects being handledMeans for controlling flow of coolant through channel being serviced
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
2.
SUPERCRITICAL WATER OXIDATION TO TREAT BIOMASS AND ORGANIC WASTE TO PRODUCE CHEMICAL PRODUCTS AND SODIUM FORMATE
An integrated energy system comprising a power plant including at least one nuclear reactor and an electrical power generation system, the at least one nuclear reactor being configured to generate steam, and a supercritical water oxidation system operably coupled to the power plant. The supercritical water oxidation system including a desalination plant configured to produce first water and brine, a chlor-alkali membrane process configured to receive the brine and produce at least a Sodium Hydroxide solution, a reactor configured to receive the first water, the steam, and the Sodium Hydroxide solution to produce a waste solution and a solid waste, and a separator configured to receive the waste solution and produce Carbon Dioxide and second water.
C07C 29/151 - Preparation of compounds having hydroxy or O-metal groups bound to a carbon atom not belonging to a six-membered aromatic ring by reduction of oxides of carbon exclusively with hydrogen or hydrogen-containing gases
C07C 29/151 - Preparation of compounds having hydroxy or O-metal groups bound to a carbon atom not belonging to a six-membered aromatic ring by reduction of oxides of carbon exclusively with hydrogen or hydrogen-containing gases
G21D 9/00 - Arrangements to provide heat for purposes other than conversion into power, e.g. for heating buildings
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
H02J 3/46 - Controlling the sharing of output between the generators, converters, or transformers
C07C 51/41 - Preparation of salts of carboxylic acids by conversion of the acids or their salts into salts with the same carboxylic acid part
A mount support system comprising a base having a first end and a second end opposite the first end. The base including a first surface configured to engage a clamp, a second surface configured to engage with an installation surface, a first T-slot extending at from the first end toward a center of the base, and a second T-slot extending from the second end toward the center of the base. The clamp including a lower portion configured to engage with the base, and an upper portion configured to engage with the lower portion, at least one fastener extending through the clamp configured to engage with at least one of the first T-slot and the second T-slot, and configured to penetrate the lower portion of the clamp and the upper portion of the clamp, and at least one fastening device configured to couple with the at least one fastener.
A mount support system comprising a base having a first end and a second end opposite the first end. The base including a first surface configured to engage a clamp, a second surface configured to engage with an installation surface, a first T-slot extending at from the first end toward a center of the base, and a second T-slot extending from the second end toward the center of the base. The clamp including a lower portion configured to engage with the base, and an upper portion configured to engage with the lower portion, at least one fastener extending through the clamp configured to engage with at least one of the first T-slot and the second T-slot, and configured to penetrate the lower portion of the clamp and the upper portion of the clamp, and at least one fastening device configured to couple with the at least one fastener.
G21C 13/024 - Supporting constructions for pressure vessels or containment vessels
F16L 3/10 - Supports for pipes, cables or protective tubing, e.g. hangers, holders, clamps, cleats, clips, brackets substantially surrounding the pipe, cable or protective tubing divided, i.e. with two members engaging the pipe, cable or protective tubing
6.
NUCLEAR REACTOR SYSTEM BASED INDIRECT HEAT CYCLE MANAGEMENT
An integrated system comprising a nuclear power module to output initial steam, a turbine generator to receive the initial steam and output first steam, a first heat exchanger and a second heat exchanger. The first heat exchanger is configured to receive water, receive the first steam, and transfer heat from the first steam into the water to create second steam, and the second heat exchanger is configured to receive the second steam, and convert the second steam to a third steam.
F01K 11/02 - Steam engine plants characterised by the engines being structurally combined with boilers or condensers the engines being turbines
F01K 13/00 - General layout or general methods of operation, of complete steam engine plants
F01K 23/10 - Plants characterised by more than one engine delivering power external to the plant, the engines being driven by different fluids the engine cycles being thermally coupled combustion heat from one cycle heating the fluid in another cycle with exhaust fluid of one cycle heating the fluid in another cycle
7.
NUCLEAR DRIVEN HYDROTHERMAL DECOMPOSITION OF AN INERT SODIUM SALT FOR THE PRODUCTION OF HYDROGEN
Methods and systems for hydrogen production from inert sodium salts are described herein. In an example method, steam is generated by a nuclear reactor power plant system. The steam is applied to sodium formate to facilitate one or more thermal and/or hydrothermal decomposition processes, thereby generating hydrogen. In the example method, sodium formate is generated by combining sodium hydroxide generated by an electrolysis process with sodium carbonate and/or sodium bicarbonate generated by a carbon capture process. Embodiments can be used to supply hydrogen storage facilities and/or for energy production.
C01B 3/32 - Production of hydrogen or of gaseous mixtures containing hydrogen by reaction of gaseous or liquid organic compounds with gasifying agents, e.g. water, carbon dioxide, air
C07C 51/41 - Preparation of salts of carboxylic acids by conversion of the acids or their salts into salts with the same carboxylic acid part
H01M 8/0612 - Combination of fuel cells with means for production of reactants or for treatment of residues with means for production of gaseous reactants from carbon-containing material
H01M 8/18 - Regenerative fuel cells, e.g. redox flow batteries or secondary fuel cells
C02F 1/461 - Treatment of water, waste water, or sewage by electrochemical methods by electrolysis
C01B 3/22 - Production of hydrogen or of gaseous mixtures containing hydrogen by decomposition of gaseous or liquid organic compounds
H01M 8/12 - Fuel cells with solid electrolytes operating at high temperature, e.g. with stabilised ZrO2 electrolyte
9.
THERMAL DECOMPOSITION OF SODIUM FORMATE AND SODIUM OXALATE USING SUPER-HEATED STEAM FROM NUCLEAR REACTOR SYSTEM FOR DIRECT IN-SITU METHANOL PRODUCTION
An integrated energy system including a power plant is discussed herein. In some examples, the integrated energy system may include at least one nuclear reactor and electrical power generation system configured to generate steam and electricity, a water treatment plant configured to produce Sodium Hydroxide (NaOH) from salt water, a Sodium Formate (HCOONa) production plant configured to receive the Sodium Hydroxide (NaOH) to produce Sodium Formate (HCOONa), a Thermal Decomposition reactor configured to receive the Sodium Formate (HCOONa) and configured to receive at least a first portion of the steam or at least a second portion of the electricity from the power plant to indirectly heat the Thermal Decomposition reactor to produce Hydrogen (H2), Carbon Dioxide (CO2), and Carbon Monoxide (CO) from the Sodium Formate (HCOONa), and a Methanol (CH3OH) reaction chamber configured to receive the Hydrogen (H2), the Carbon Dioxide (CO2), and the Carbon Monoxide (CO) to produce Methanol (CH3OH).
C07C 29/151 - Preparation of compounds having hydroxy or O-metal groups bound to a carbon atom not belonging to a six-membered aromatic ring by reduction of oxides of carbon exclusively with hydrogen or hydrogen-containing gases
C07C 51/41 - Preparation of salts of carboxylic acids by conversion of the acids or their salts into salts with the same carboxylic acid part
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
G21D 9/00 - Arrangements to provide heat for purposes other than conversion into power, e.g. for heating buildings
H02J 3/46 - Controlling the sharing of output between the generators, converters, or transformers
10.
NUCLEAR PROCESS STEAM DRIVEN HYDROTHERMAL DECOMPOSITION OF METHANE FOR LOW-TEMPERATURE GREEN METHANOL PRODUCTION
An integrated energy system including a power plant is discussed herein. In some examples, the integrated energy system may include a power plant configured to generate steam, a hydrothermal decomposition reactor configured to receive at least a portion of the steam (H2O) from the power plant to react with Methane (CH4) within the hydrothermal decomposition reactor to produce Hydrogen (H2) and Carbon Dioxide (CO2), a first separation unit configured to separate the Hydrogen (H2) and the Carbon Dioxide (CO2), a Solid Oxide Stack configured to receive at least a portion of the Carbon Dioxide (CO2) and to produce Carbon Monoxide (CO), a second separation unit configured to separate the Carbon Dioxide (CO2) from the Carbon Monoxide (CO), and a methanol synthesis reactor configured to receive at least a portion of the Hydrogen (H2) and at least a portion of the Carbon Monoxide (CO) to produce Methanol (CH3OH).
C07C 29/152 - Preparation of compounds having hydroxy or O-metal groups bound to a carbon atom not belonging to a six-membered aromatic ring by reduction of oxides of carbon exclusively with hydrogen or hydrogen-containing gases characterised by the reactor used
B01J 19/24 - Stationary reactors without moving elements inside
An integrated energy system comprising a power plant including at least one nuclear reactor and an electrical power generation system, the at least one nuclear reactor being configured to generate steam, and a supercritical water oxidation system operably coupled to the power plant. The supercritical water oxidation system including a desalination plant configured to produce first water and brine, a chlor-alkali membrane process configured to receive the brine and produce at least a Sodium Hydroxide solution, a reactor configured to receive the first water, the steam, and the Sodium Hydroxide solution to produce a waste solution and a solid waste, and a separator configured to receive the waste solution and produce Carbon Dioxide and second water.
A nuclear reactor is discussed herein. In some examples, the nuclear reactor may comprise an inner-core region, including liquid fuel, coolant/moderator, and a hydrogen vapor space, an out-of-core region surrounding the inner-core region, the out-of-core region including, an inner reflector adjacent to the inner-core region, the inner reflector including a first irradiation facility, and an outer reflector adjacent to the inner reflector, the outer reflector including a second irradiation facility.
G21G 1/08 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes outside of nuclear reactors or particle accelerators by neutron irradiation accompanied by nuclear fission
G21C 5/02 - Moderator or core structureSelection of materials for use as moderator Details
G21C 5/12 - Moderator or core structureSelection of materials for use as moderator characterised by composition, e.g. the moderator containing additional substances which ensure improved heat resistance of the moderator
G21C 5/18 - Moderator or core structureSelection of materials for use as moderator characterised by the provision of more than one active zone
G21C 11/06 - Reflecting shields, i.e. for minimising loss of neutrons
13.
NUCLEAR PROCESS STEAM DRIVEN HYDROTHERMAL DECOMPOSITION OF METHANE FOR LOW-TEMPERATURE GREEN METHANOL PRODUCTION
C25B 1/042 - Hydrogen or oxygen by electrolysis of water by electrolysis of steam
G21D 5/00 - Arrangements of reactor and engine in which reactor-produced heat is converted into mechanical energy
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
14.
NUCLEAR REACTOR-BASED SYSTEMS, METHODS, AND DEVICES FOR ENERGY PRODUCTION AND CARBON DIOXIDE (CO2) CAPTURE
An integrated energy system comprising a power plant configured to generate steam. The power plant can include a nuclear reactor and/or an electrical power generation system. A chemical products generation system can include a first reaction chamber receiving Sodium Formate (HCOONa) that, via insertion of a first portion of the steam at a first temperature, is decomposed into Sodium Oxalate ((COO)2Na2) and Hydrogen (H2), the steam including super-heated steam. The chemical products generation system can include a second reaction chamber receiving the Sodium Oxalate ((COO)2Na2) that, via insertion of a second portion of the steam at a second temperature, is decomposed into Sodium Oxide (Na2O), Carbon Monoxide (CO), and Carbon Dioxide (CO2). A syngas generation system can be operably coupled to the chemical products generation system and configured to generate a combination of the Hydrogen (H2), the Carbon Monoxide (CO), and/or the Carbon Dioxide (CO2), and/or to generate syngas.
C01B 3/34 - Production of hydrogen or of gaseous mixtures containing hydrogen by reaction of gaseous or liquid organic compounds with gasifying agents, e.g. water, carbon dioxide, air by reaction of hydrocarbons with gasifying agents
An integrated energy system comprising a power plant including at least one nuclear reactor and an electrical power generation system a syngas generation system operably coupled to the power plant, the syngas generation system comprising a first reaction chamber configured to receive Sodium Formate (HCOONa), and a second reaction chamber configured to receive Sodium Oxalate ((COO)2Na2), and a methanol generation system operably coupled to the syngas generation system.
C01B 3/34 - Production of hydrogen or of gaseous mixtures containing hydrogen by reaction of gaseous or liquid organic compounds with gasifying agents, e.g. water, carbon dioxide, air by reaction of hydrocarbons with gasifying agents
A method for Carbon Dioxide (CO2) production comprising producing super-heated steam, utilizing a small modular nuclear reactor power plant system, receiving Sodium Formate (HCOONa) into a first reaction chamber, the first reaction chamber receiving a first portion of the super-heated steam at a first temperature, decomposing the Sodium Formate (HCOONa) into Sodium Oxalate ((COO)2Na2) and Hydrogen (H2), receiving the Sodium Oxalate ((COO)2Na2) into a second reaction chamber, the second reaction chamber receiving a second portion of the super-heated steam at a second temperature, decomposing the Sodium Oxalate ((COO)2Na2) into Sodium Oxide (Na2O), Carbon Monoxide (CO), and Carbon Dioxide (CO2).
C01B 3/34 - Production of hydrogen or of gaseous mixtures containing hydrogen by reaction of gaseous or liquid organic compounds with gasifying agents, e.g. water, carbon dioxide, air by reaction of hydrocarbons with gasifying agents
An integrated energy system comprising a power plant including at least one nuclear reactor and electrical power generation system, the at least one nuclear reactor being configured to generate steam, and the electrical power generation system being configured to generate electricity, a desalination system configured to receive at least a portion of the electricity and steam to produce brine, an electrolysis process configured to process the brine into Sodium Hydroxide (NaOH), a Sodium Formate (HCOONa) production process configured to receive the Sodium Hydroxide (NaOH) to produce Sodium Formate (HCOONa), a Hydrogen (H2) extraction reactor configured to receive the Sodium Formate (HCOONa) and produce Hydrogen (H2), and a fuel cell configured to receive the Hydrogen (H2).
H01M 8/0606 - Combination of fuel cells with means for production of reactants or for treatment of residues with means for production of gaseous reactants
C01B 3/22 - Production of hydrogen or of gaseous mixtures containing hydrogen by decomposition of gaseous or liquid organic compounds
C01B 3/56 - Separation of hydrogen or hydrogen containing gases from gaseous mixtures, e.g. purification by contacting with solidsRegeneration of used solids
C07C 29/15 - Preparation of compounds having hydroxy or O-metal groups bound to a carbon atom not belonging to a six-membered aromatic ring by reduction of oxides of carbon exclusively
C07C 51/41 - Preparation of salts of carboxylic acids by conversion of the acids or their salts into salts with the same carboxylic acid part
Described herein are techniques that may be performed in an Integrated Energy System (IES). The IES may include a clean water production plant, a supercritical water source, a waste source, a Sodium Hydroxide source, and a reaction chamber. The reaction chamber may be configured to receive supercritical water from the supercritical water source, waste from the waste source, and Sodium Hydroxide from the Sodium Hydroxide source to an interior of the reaction chamber. The reaction chamber may be configured to maintain a supercritical temperature and pressure within the interior of the reaction chamber and to convert the waste into Carbon Dioxide and Water in a Super Critical Water Oxidation (SCWO) reaction.
An apparatus including an integrated system, which can include a nuclear reactor; and a containment isolation system configured to prevent release of radioactive material from the nuclear reactor. The containment isolation system can include a containment vessel and a containment isolation test valve. The containment isolation test valve can include a body having a first test port and a first test port plug. The containment isolation test valve can include a cover configured to couple with the body, the cover having, a first seal, a second seal, an area between the first seal and the second seal, a second test port, and a second test port plug. The containment isolation system can include a containment isolation valve.
An apparatus including an integrated system, which can include a nuclear reactor; and a containment isolation system configured to prevent release of radioactive material from the nuclear reactor. The containment isolation system can include a containment vessel and a containment isolation test valve. The containment isolation test valve can include a body having a first test port and a first test port plug. The containment isolation test valve can include a cover configured to couple with the body, the cover having, a first seal, a second seal, an area between the first seal and the second seal, a second test port, and a second test port plug. The containment isolation system can include a containment isolation valve.
G01M 3/32 - Investigating fluid tightness of structures by using fluid or vacuum by measuring rate of loss or gain of fluid, e.g. by pressure-responsive devices, by flow detectors for containers, e.g. radiators
G21C 13/073 - Closures for reactor-vessels, e.g. rotatable
G21C 13/10 - Means for preventing contamination in event of leakage
21.
THERMAL POWER CONVERSION SYSTEMS INCLUDING HEAT PIPES AND PHOTOVOLTAIC CELLS
Power generation systems, such as nuclear power generation systems, are described herein. A representative power generation system includes a heat source, a heat pipe, and a thermophotovoltaic cell. The heat pipe includes a first region and a second region. The first region is positioned to absorb heat from the heat source, and the second region is positioned to radiate at least a portion of the absorbed heat away from the heat pipe as thermal radiation. The thermophotovoltaic cell is positioned to receive the thermal radiation from the second region of the heat pipe and to convert at least a portion of the thermal radiation to electrical energy. The power generation system can further include another heat pipe positioned to remove waste heat from the thermophotovoltaic cell.
Pressure vessels and closures for pressure vessels, such as for use in nuclear reactor systems, are described herein. A representative pressure vessel includes (i) a first enclosure including a first flange having a lower surface and a first inner surface, and (ii) a second enclosure including a second flange having an upper surface and a second inner surface. The pressure vessel can further include a sealing member having a first portion and a second portion. The first portion is configured to contact both the lower surface of the first flange and the upper surface of the second flange to provide a first seal between the first and second enclosures. The second portion is configured to contact, via an interference fit, both the first inner surface of the first flange and the second inner surface of the second flange to provide a second seal between the first and second enclosures.
Described herein are techniques that may be performed in an Integrated Energy System (IES). The IES may include a power plant, an emission source, and a chemical processing plant. The IES may include one or more sub-plants configured to receive Carbon Dioxide from an emission source, convert a first portion of the Carbon Dioxide into Carbon Monoxide, receive Sodium Hydroxide, combine the Carbon Monoxide and the Sodium Hydroxide to produce Hydrogen gas, and combine, using a reaction chamber, a second portion of the Carbon Dioxide, the Carbon Monoxide, and the Hydrogen to produce Methanol.
B01D 53/32 - Separation of gases or vapoursRecovering vapours of volatile solvents from gasesChemical or biological purification of waste gases, e.g. engine exhaust gases, smoke, fumes, flue gases or aerosols by electrical effects other than those provided for in group
C07C 29/151 - Preparation of compounds having hydroxy or O-metal groups bound to a carbon atom not belonging to a six-membered aromatic ring by reduction of oxides of carbon exclusively with hydrogen or hydrogen-containing gases
Described herein are techniques that may be performed in an Integrated Energy System (IES). The IES may include a power plant, an emission source, and a chemical processing plant. The IES may include one or more sub-plants configured to receive Carbon Dioxide from an emission source, convert a first portion of the Carbon Dioxide into Carbon Monoxide, receive Sodium Hydroxide, combine the Carbon Monoxide and the Sodium Hydroxide to produce Hydrogen gas, and combine, using a reaction chamber, a second portion of the Carbon Dioxide, the Carbon Monoxide, and the Hydrogen to produce Methanol.
C07C 29/151 - Preparation of compounds having hydroxy or O-metal groups bound to a carbon atom not belonging to a six-membered aromatic ring by reduction of oxides of carbon exclusively with hydrogen or hydrogen-containing gases
C02F 1/44 - Treatment of water, waste water, or sewage by dialysis, osmosis or reverse osmosis
A reactor vessel that includes a reactor core mounted within a volume of the reactor vessel, the reactor core comprising one or more nuclear fuel assemblies configured to generate a nuclear fission reaction, a riser positioned above the reactor core, the riser forming a primary coolant flow path, a steam generator thermally coupled to the riser, the steam generator communicatively coupled to a steam turbine through a steam inlet that includes a steam inlet valve, a secondary coolant flow path that extends through the steam generator, the secondary coolant flow path coupled to a coolant pump, and a control system coupled to both the steam inlet valve and the coolant pump, the control system configured to control a power output of the nuclear fission reaction by adjusting one or more parameters of the steam inlet valve or the coolant pump.
G21C 1/02 - Fast fission reactors, i.e. reactors not using a moderator
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 7/22 - 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 7/24 - Selection of substances for use as neutron-absorbing material
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 13/02 - Pressure vesselsContainment vesselsContainment in general Details
An integrated system for indirect cycle steam heating comprising a nuclear power module configured to output first steam; a turbine generator configured to receive the first steam and output second steam; a heat exchanger configured to receive water, receive at least one of first steam, second steam, and transfer heat from the at least one of first steam and second steam into the water to create third steam a peaking heater configured to receive the third steam, transfer augmenting heat into the third steam, and heat, based at least in part on the transfer, the third steam to have a temperature above a threshold temperature an auxiliary heater configured to receive the third steam; and a chemical processing plant configured to receive the third steam and transfer heat from the third steam into a chemical.
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
F22B 37/00 - Component parts or details of steam boilers
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
27.
Nuclear reactor system based indirect heat cycle management
An integrated system for indirect cycle steam heating comprising a nuclear power module configured to output first steam; a turbine generator configured to receive the first steam and output second steam; a heat exchanger configured to receive water, receive at least one of first steam, second steam, and transfer heat from the at least one of first steam and second steam into the water to create third steam a peaking heater configured to receive the third steam, transfer augmenting heat into the third steam, and heat, based at least in part on the transfer, the third steam to have a temperature above a threshold temperature an auxiliary heater configured to receive the third steam; and a chemical processing plant configured to receive the third steam and transfer heat from the third steam into a chemical.
F01K 11/02 - Steam engine plants characterised by the engines being structurally combined with boilers or condensers the engines being turbines
F01K 13/00 - General layout or general methods of operation, of complete steam engine plants
F01K 23/10 - Plants characterised by more than one engine delivering power external to the plant, the engines being driven by different fluids the engine cycles being thermally coupled combustion heat from one cycle heating the fluid in another cycle with exhaust fluid of one cycle heating the fluid in another cycle
28.
SUPPORTS WITH INTEGRATED SENSORS FOR NUCLEAR REACTOR STEAM GENERATORS, AND ASSOCIATED SYSTEMS AND METHODS
The disclosure is directed to a system and techniques for integrating sensors within a generator support to detect fluctuations. Such techniques may be performed by a device that includes at least one fiber optic sensor and may comprise receiving, via the at least one fiber optic sensor, an optical signal transmitted over at least one fiber optic link integrally formed with a conduit support, the conduit support coupled with a steam generator conduit. The techniques may further comprise generating, based on the optical signal, strain data related to the steam generator conduit, and based on the generated strain data, determine one or more oscillatory characteristic of a steam generator associated with the steam generator conduit.
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
F28D 7/02 - Heat-exchange apparatus having stationary tubular conduit assemblies for both heat-exchange media, the media being in contact with different sides of a conduit wall the conduits being helically coiled
F28F 9/00 - CasingsHeader boxesAuxiliary supports for elementsAuxiliary members within casings
G21C 17/10 - Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
29.
INTEGRATED ENERGY SYSTEMS INCLUDING TECHNIQUES FOR ACHIEVING STEAM PRODUCTION FOR USE IN RESOURCE PRODUCTION
Described herein are techniques that may be performed in an Integrated Energy System (IES). The IES may include a power production plant, one or more power modules, a steam conditioning plant, an integrated energy system controller and one or more processors. The techniques include receiving first information about steam and electrical power generated by the power production plant, receiving second information about a resource production target from the resource production plant, determining a target temperature, a target pressure, and a target flow rate of steam needed to achieve the resource production target, determining at least one of a level of compression or heating to be applied to a first portion of steam generated by the power production plant; and causing a portion of the electrical power to apply the level of compression or heating to the first portion of steam.
A nuclear power system includes a reactor vessel that includes a reactor core that includes nuclear fuel assemblies configured to generate a nuclear fission reaction; a riser positioned above the reactor core; a primary coolant flow path that extends from a bottom portion of the volume through the reactor core and through an annulus between the riser and the reactor vessel; a primary coolant that circulates through the primary coolant flow path to receive heat from the nuclear fission reaction and release the heat to generate electric power in a power generation system; and a control rod assembly system positioned in the reactor vessel and configured to position control rods in only two discrete positions.
G21C 1/02 - Fast fission reactors, i.e. reactors not using a moderator
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 7/22 - 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 7/24 - Selection of substances for use as neutron-absorbing material
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 13/02 - Pressure vesselsContainment vesselsContainment in general Details
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
C01B 3/32 - Production of hydrogen or of gaseous mixtures containing hydrogen by reaction of gaseous or liquid organic compounds with gasifying agents, e.g. water, carbon dioxide, air
G21D 9/00 - Arrangements to provide heat for purposes other than conversion into power, e.g. for heating buildings
C07C 29/151 - Preparation of compounds having hydroxy or O-metal groups bound to a carbon atom not belonging to a six-membered aromatic ring by reduction of oxides of carbon exclusively with hydrogen or hydrogen-containing gases
C07C 51/41 - Preparation of salts of carboxylic acids by conversion of the acids or their salts into salts with the same carboxylic acid part
Described herein are techniques that may be performed in an Integrated Energy System (IES) to produce Nitric Acid (HNO3) while minimizing a carbon footprint. Such techniques, as performed by a resource production plant, may comprise receiving electricity and steam from a power plant to produce Hydrogen (H2) gas from the steam at a Hydrogen (H2) production sub-plant, receiving electricity from the power plant and air from the environment to produce Nitrogen (N2) gas at a Nitrogen (N2) production sub-plant, producing Ammonia (NH3) from the Hydrogen (H2) gas and the Nitrogen (N2) gas at a nitrogen production sub-plant, and producing Nitric Acid (HNO3) from the Ammonia (NH3) at a Nitric Acid (HNO3) production sub-plant.
A nuclear reactor module, comprising a reactor pressure vessel including a removably attached lower reactor vessel head configured to house a reactor core; a lower reactor vessel head removably attached to the reactor pressure vessel and configured to house the reactor core; a containment vessel encapsulating the reactor pressure vessel; and a lower containment head removably attached to the containment vessel and configured to house the lower reactor vessel head, the containment vessel and the reactor pressure vessel being configured to be lifted and transported between a reactor bay and a refueling bay within a nuclear reactor building via a crane.
G21C 19/18 - Apparatus for bringing fuel elements to the reactor charge area, e.g. from a storage place
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 1/32 - 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
G21C 13/02 - Pressure vesselsContainment vesselsContainment in general Details
G21C 17/10 - Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
G21C 19/20 - Arrangements for introducing objects into the pressure vesselArrangements for handling objects within the pressure vesselArrangements for removing objects from the pressure vessel
G21C 19/32 - Apparatus for removing radioactive objects or materials from the reactor discharge area, e.g. to a storage placeApparatus for handling radioactive objects or materials within a storage place or removing them therefrom
A power module assembly may include a reactor vessel containing a primary coolant and one or more inlets configured to draw a secondary coolant from the containment cooling pool in response to a loss of power and/or a loss of coolant. One or more outlets may be submerged in the containment cooling pool and may be configured to vent the secondary coolant into the containment cooling pool. A heat exchanger may be configured to remove heat from the primary coolant, wherein the heat may be removed by circulating the secondary coolant from the containment cooling pool through the heat exchanger via natural circulation.
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
G21C 15/26 - Promoting flow of the coolant by convection, e.g. using chimneys, using divergent channels
36.
SMALL MODULAR NUCLEAR REACTOR INTEGRATED ENERGY SYSTEMS FOR CAPTURING ATMOSPHERIC CARBON DIOXIDE USING SODIUM HYDROXIDE
Integrated Energy Systems (IESs), such as for use in capturing atmospheric carbon dioxide, and associated devices and methods are described herein. A representative IES can include a power plant system having multiple modular nuclear reactors, a desalination plant, a brine processing plant, and a direct air capture plant. The nuclear reactors can generate electricity and/or steam for use by the desalination plant and the direct air capture plant. The desalination plant can use the electricity and/or steam to produce brine from seawater or brackish water. The brine processing plant can receive the brine from the desalination plant and process the brine to produce sodium hydroxide. The direct air capture plant can use the sodium hydroxide as a liquid sorbent in a direct air capture process to capture carbon dioxide from atmospheric air.
B01D 53/14 - Separation of gases or vapoursRecovering vapours of volatile solvents from gasesChemical or biological purification of waste gases, e.g. engine exhaust gases, smoke, fumes, flue gases or aerosols by absorption
C02F 1/44 - Treatment of water, waste water, or sewage by dialysis, osmosis or reverse osmosis
C25B 1/46 - Simultaneous production of alkali metal hydroxides and chlorine, oxyacids or salts of chlorine, e.g. by chlor-alkali electrolysis in diaphragm cells
F01K 3/18 - Plants characterised by the use of steam or heat accumulators, or intermediate steam heaters, therein having heaters
37.
SMALL MODULAR NUCLEAR REACTOR INTEGRATED ENERGY SYSTEMS FOR CAPTURING ATMOSPHERIC CARBON DIOXIDE USING SODIUM HYDROXIDE
Integrated Energy Systems (IESs), such as for use in capturing atmospheric carbon dioxide, and associated devices and methods are described herein. A representative IES can include a power plant system having multiple modular nuclear reactors, a desalination plant, a brine processing plant, and a direct air capture plant. The nuclear reactors can generate electricity and/or steam for use by the desalination plant and the direct air capture plant. The desalination plant can use the electricity and/or steam to produce brine from seawater or brackish water. The brine processing plant can receive the brine from the desalination plant and process the brine to produce sodium hydroxide. The direct air capture plant can use the sodium hydroxide as a liquid sorbent in a direct air capture process to capture carbon dioxide from atmospheric air.
B01D 53/14 - Separation of gases or vapoursRecovering vapours of volatile solvents from gasesChemical or biological purification of waste gases, e.g. engine exhaust gases, smoke, fumes, flue gases or aerosols by absorption
C02F 1/44 - Treatment of water, waste water, or sewage by dialysis, osmosis or reverse osmosis
C02F 1/46 - Treatment of water, waste water, or sewage by electrochemical methods
Passive emergency core cooling systems (ECCSs) for use in nuclear power systems and associated devices and methods are disclosed herein. An ECCS can include a passive chemical dissolution system that passively collects and directs condensate formed on an inner wall of a containment vessel during an emergency event to a dissolver housing containing a neutron-absorbing chemical. The neutron-absorbing chemical, once dissolved by the condensate, can be released into a recirculating coolant to cool down the reactor core. The ECCS can include a passive mixing system that passively collects and directs condensate to a bottom of the containment vessel. The bottom of the open volume may include colder coolant and/or higher concentration of the neutron-absorbing chemical. The condensate can push the colder coolant and/or the concentrated chemical upward for improved circulation.
Structures for forming a module, such as a module for use in a nuclear reactor building, and associated systems and methods are described herein. A representative structure can include a first plate, a second plate spaced apart from and positioned parallel to the first plate, and a support assembly positioned between the first and second plates. The support assembly can include a column, a first beam extending from the column parallel to the first and second plates, and a second beam extending from the column parallel to the first and second plates. The panel structure can further include a plurality of spaced apart joint plates extending between and connecting the first and second plates. The joint plates can support the first beam and the second beam. The panel structure can further include a fill material between the first and second plates and surrounding the support assembly and the joint plates.
Integrated energy systems, such as for use in producing sodium formate and/or processing sodium formate to generate hydrogen as an energy carrier and that produce few or no carbon emissions, and associated devices and methods are described herein. A representative integrated energy system can include a power plant system having multiple modular nuclear reactors. The nuclear reactors can generate electricity and steam for direct use in a sodium formate process or for use in an electrical power conversion system to generate electricity for use in the sodium formate process or for supply to a power grid. Individual ones of the nuclear reactors can be configured to flexibly generate differing outputs of steam or electricity based on a demand state of the power grid—for example, supplying excess electricity and/or steam to the sodium formate process during off-peak hours.
Integrated energy systems, such as for use in producing sodium formate and/or processing sodium formate to generate hydrogen as an energy carrier and that produce few or no carbon emissions, and associated devices and methods are described herein. A representative integrated energy system can include a power plant system having multiple modular nuclear reactors. The nuclear reactors can generate electricity and steam for direct use in a sodium formate process or for use in an electrical power conversion system to generate electricity for use in the sodium formate process or for supply to a power grid. Individual ones of the nuclear reactors can be configured to flexibly generate differing outputs of steam or electricity based on a demand state of the power grid—for example, supplying excess electricity and/or steam to the sodium formate process during off-peak hours.
Integrated energy systems, such as for use in green industrial processes that produce few or no carbon emissions, and associated devices and methods are described herein. A representative integrated energy system can include a power plant system having multiple modular nuclear reactors. The nuclear reactors can generate steam for direct industrial use or for use in an electrical power conversion system to generate electricity. Individual ones of the nuclear reactors can be configured to flexibly generate differing outputs of steam or electricity based on the vary requirements of the industrial processes of the integrated energy system. The industrial processes can include, for example, the production of hydrogen, oxygen, nitrogen, ammonia, urea, sulfur, sulfuric acid, and/or other useful chemicals.
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
A nuclear reactor protection system includes a plurality of functionally independent modules, each of the modules configured to receive a plurality of inputs from a nuclear reactor safety system, and logically determine a safety action based at least in part on the plurality of inputs, each of the functionally independent modules comprising a digital module or a combination digital and analog module, an analog module electrically coupled to one or more of the functionally independent modules, and one or more nuclear reactor safety actuators communicably coupled to the plurality of functionally independent modules to receive the safety action determination based at least in part on the plurality of inputs.
Structures for forming a module, such as a module for use in a nuclear reactor building, and associated systems and methods are described herein. A representative structure can include a first plate, a second plate spaced apart from and positioned parallel to the first plate, and a support assembly positioned between the first and second plates. The support assembly can include a column, a first beam extending from the column parallel to the first and second plates, and a second beam extending from the column parallel to the first and second plates. The panel structure can further include a plurality of spaced apart joint plates extending between and connecting the first and second plates. The joint plates can support the first beam and the second beam. The panel structure can further include a fill material between the first and second plates and surrounding the support assembly and the joint plates.
E04B 2/00 - Walls, e.g. partitions, for buildingsWall construction with regard to insulationConnections specially adapted to walls
E04B 2/56 - Walls of framework or pillarworkWalls incorporating load-bearing elongated members
E04B 2/58 - Walls of framework or pillarworkWalls incorporating load-bearing elongated members with elongated members of metal
E04B 2/60 - Walls of framework or pillarworkWalls incorporating load-bearing elongated members with elongated members of metal characterised by special cross-section of the elongated members
E04B 2/84 - Walls made by casting, pouring, or tamping in situ
E04B 2/86 - Walls made by casting, pouring, or tamping in situ made in permanent forms
E02D 29/00 - Underground or underwater structuresRetaining walls
E04B 1/00 - Constructions in generalStructures which are not restricted either to walls, e.g. partitions, or floors or ceilings or roofs
E04B 1/62 - Insulation or other protectionElements or use of specified material therefor
E04B 1/92 - Protection against other undesired influences or dangers
E04B 1/98 - Protection against other undesired influences or dangers against vibrations or shocksProtection against other undesired influences or dangers against mechanical destruction, e.g. by air-raids
45.
NUCLEAR REACTORS HAVING LIQUID METAL ALLOY FUELS AND/OR MODERATORS
Nuclear reactor systems and associated devices and methods are described herein. A representative nuclear reactor system includes a reactor vessel having a barrier separating a core region from a shield region. A plurality of fuel rods containing a liquid nuclear fuel are positioned in the core region. A liquid moderator material is also positioned in the core region at least partially around the fuel rods. A plurality of heat exchangers can be positioned in the shield region, and a plurality of heat pipes can extend through the barrier. The moderator material is positioned to transfer heat received from the liquid nuclear fuel to the heat pipes, and the heat pipes are positioned to transfer heat received from the moderator material to the heat exchangers. The heat exchangers can transport the heat out of the system for use in one or more processes, such as generating electricity.
Nuclear reactor systems and associated devices and methods are described herein. A representative nuclear reactor system includes a heat pipe network having an evaporator region, an adiabatic region, and a condenser region. The heat pipe network can define a plurality of flow paths having an increasing cross-sectional flow area in a direction from the evaporator region toward the condenser region. The system can further include nuclear fuel thermally coupled to at least a portion of the evaporator region. The heat pipe network is positioned to transfer heat received from the fuel at the evaporator region, to the condenser region. The system can further include one or more heat exchangers thermally coupled to the evaporator region for transporting the heat out of the system for use in one or more processes, such as generating electricity.
G21C 15/257 - Promoting flow of the coolant using heat-pipes
F28D 15/02 - Heat-exchange apparatus with the intermediate heat-transfer medium in closed tubes passing into or through the conduit walls in which the medium condenses and evaporates, e.g. heat-pipes
Integrated energy systems, such as for use in green industrial processes that produce few or no carbon emissions, and associated devices and methods are described herein. A representative integrated energy system can include a power plant system having multiple modular nuclear reactors. The nuclear reactors can generate steam for direct industrial use or for use in an electrical power conversion system to generate electricity. Individual ones of the nuclear reactors can be configured to flexibly generate differing outputs of steam or electricity based on the vary requirements of the industrial processes of the integrated energy system. The industrial processes can include, for example, the production of hydrogen, oxygen, nitrogen, ammonia, urea, sulfur, sulfuric acid, and/or other useful chemicals.
C25B 9/65 - Means for supplying currentElectrode connectionsElectric inter-cell connections
G21D 9/00 - Arrangements to provide heat for purposes other than conversion into power, e.g. for heating buildings
F22G 1/16 - Steam superheating characterised by heating method by using a separate heat source independent from heat supply of the steam boiler, e.g. by electricity, by auxiliary combustion of fuel oil
C25B 9/70 - Assemblies comprising two or more cells
C25B 1/042 - Hydrogen or oxygen by electrolysis of water by electrolysis of steam
A nuclear reactor protection system includes a plurality of functionally independent modules, each of the modules configured to receive a plurality of inputs from a nuclear reactor safety system, and logically determine a safety action based at least in part on the plurality of inputs; and one or more nuclear reactor safety actuators communicably coupled to the plurality of functionally independent modules to receive the safety action determination based at least in part on the plurality of inputs.
G21D 3/06 - Safety arrangements responsive to faults within the plant
H02H 3/05 - Emergency protective circuit arrangements for automatic disconnection directly responsive to an undesired change from normal electric working condition, with or without subsequent reconnection Details with means for increasing reliability, e.g. redundancy arrangements
49.
Small modular nuclear reactor integrated energy systems for industrial applications, such as enhanced oil recovery operations
Integrated energy systems, such as for use in enhanced oil recovery operations, and associated devices and methods are described herein. A representative integrated energy system can include a power plant system having multiple modular nuclear reactors. The nuclear reactors can generate steam for direct industrial use or for use in an electrical power conversion system to generate electricity. Individual ones of the nuclear reactors can be configured to generate steam or electricity based on the requirements of different stages of the oil recovery operation. For example, during a first stage, a subset of the nuclear reactors can be configured to generate steam for the oil recovery operation for injection into an oil reservoir. During a second stage, some or all of the nuclear reactors in the subset can be reconfigured to generate electricity that can be routed to an industrial process different than the oil recovery operation.
E21B 43/24 - Enhanced recovery methods for obtaining hydrocarbons using heat, e.g. steam injection
G21D 9/00 - Arrangements to provide heat for purposes other than conversion into power, e.g. for heating buildings
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
G21C 15/257 - Promoting flow of the coolant using heat-pipes
50.
SMALL MODULAR NUCLEAR REACTOR INTEGRATED ENERGY SYSTEMS FOR INDUSTRIAL APPLICATIONS, SUCH AS ENHANCED OIL RECOVERY OPERATIONS
Integrated energy systems, such as for use in enhanced oil recovery operations, and associated devices and methods are described herein. A representative integrated energy system can include a power plant system having multiple modular nuclear reactors. The nuclear reactors can generate steam for direct industrial use or for use in an electrical power conversion system to generate electricity. Individual ones of the nuclear reactors can be configured to generate steam or electricity based on the requirements of different stages of the oil recovery operation. For example, during a first stage, a subset of the nuclear reactors can be configured to generate steam for the oil recovery operation for injection into an oil reservoir. During a second stage, some or all of the nuclear reactors in the subset can be reconfigured to generate electricity that can be routed to an industrial process different than the oil recovery operation.
A system for servicing a nuclear reactor module comprises a crane operable to attach to the nuclear reactor module, wherein the crane includes provisions for routing signals from one or more sensors of the nuclear reactor module to one or more sensor receivers.
G21C 19/32 - Apparatus for removing radioactive objects or materials from the reactor discharge area, e.g. to a storage placeApparatus for handling radioactive objects or materials within a storage place or removing them therefrom
B66C 13/46 - Position indicators for suspended loads or for crane elements
G21C 17/10 - Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
G21C 19/20 - Arrangements for introducing objects into the pressure vesselArrangements for handling objects within the pressure vesselArrangements for removing objects from the pressure vessel
B66C 13/00 - Other constructional features or details
B66C 13/06 - Auxiliary devices for controlling movements of suspended loads, or for preventing cable slack for minimising or preventing longitudinal or transverse swinging of loads
B66C 13/08 - Auxiliary devices for controlling movements of suspended loads, or for preventing cable slack for depositing loads in desired attitudes or positions
B66C 13/14 - Arrangements of means for transmitting pneumatic, hydraulic, or electric power to movable parts or devices to load-engaging elements or motors associated therewith
B66C 17/00 - Overhead travelling cranes comprising one or more substantially-horizontal girders the ends of which are directly supported by wheels or rollers running on tracks carried by spaced supports
B66C 17/06 - Overhead travelling cranes comprising one or more substantially-horizontal girders the ends of which are directly supported by wheels or rollers running on tracks carried by spaced supports specially adapted for particular purposes, e.g. in foundries, forgesOverhead travelling cranes comprising one or more substantially-horizontal girders the ends of which are directly supported by wheels or rollers running on tracks carried by spaced supports combined with auxiliary apparatus serving particular purposes
B66C 17/26 - Overhead travelling cranes comprising one or more substantially-horizontal girders the ends of which are directly supported by wheels or rollers running on tracks carried by spaced supports specially adapted for particular purposes, e.g. in foundries, forgesOverhead travelling cranes comprising one or more substantially-horizontal girders the ends of which are directly supported by wheels or rollers running on tracks carried by spaced supports combined with auxiliary apparatus serving particular purposes combined with auxiliary apparatus, e.g. log saws, pushers for unloading vehicles, means for shunting railway vehicles
B66C 19/00 - Cranes comprising trolleys or crabs running on fixed or movable bridges or gantries
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
G21C 17/06 - Devices or arrangements for monitoring or testing fuel or fuel elements outside the reactor core, e.g. for burn-up, for contamination
A system includes a containment vessel configured to prohibit a release of a coolant, and a reactor vessel mounted inside the containment vessel. An outer surface of the reactor vessel is exposed to below atmospheric pressure, wherein substantially all gases are evacuated from the containment vessel.
09 - Scientific and electric apparatus and instruments
Goods & Services
Electronic training simulators for nuclear plant employees and operators in a nuclear plant control room; Downloadable nuclear plant simulation software in the field of operation, maintenance, refueling, and calibration of nuclear power plants
54.
STRESS RELIEVING ATTACHMENT OF TUBE TO TUBESHEET, SUCH AS IN A PRESSURE VESSEL SHELL OF A NUCLEAR REACTOR POWER SYSTEM
Steam generator systems including tubesheet assemblies, such as for use in nuclear reactor systems, and associated devices and methods are described herein. A representative steam generator system can be installed in a nuclear reactor vessel positioned to house a primary coolant. The steam generator system can include a tubesheet assembly defining a plenum and comprising a tubesheet and a flexible connection portion coupling the tubesheet to the reactor vessel. The tubesheet can include a plurality of perforations fluidly coupled to the plenum. The steam generator system can further comprise a plurality of heat transfer tubes fluidly coupled to the perforations and configured to receive a flow of a secondary coolant. The connection portion can be more flexible than the tubesheet and the reactor vessel to reduce stresses on the tubesheet and the connections (e.g., tube-to-tubesheet (TTS) welds) between the tubes and the tubesheet during operation of the nuclear reactor system.
Steam generator systems including tubesheet assemblies, such as for use in nuclear reactor systems, and associated devices and methods are described herein. A representative steam generator system can be installed in a nuclear reactor vessel positioned to house a primary coolant. The steam generator system can include a tubesheet assembly defining a plenum and comprising a tubesheet and a flexible connection portion coupling the tubesheet to the reactor vessel. The tubesheet can include a plurality of perforations fluidly coupled to the plenum. The steam generator system can further comprise a plurality of heat transfer tubes fluidly coupled to the perforations and configured to receive a flow of a secondary coolant. The connection portion can be more flexible than the tubesheet and the reactor vessel to reduce stresses on the tubesheet and the connections (e.g., tube-to-tubesheet (TTS) welds) between the tubes and the tubesheet during operation of the nuclear reactor system.
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 pressure vesselArrangement 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 15/14 - 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 ducts conducting a hot fluidArrangement 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 ducts comprising auxiliary apparatus, e.g. pumps, cameras
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
G21C 15/20 - Partitions or thermal insulation between fuel channel and moderator, e.g. in pressure tube reactors
F22B 1/02 - Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers
F22B 37/00 - Component parts or details of steam boilers
A damping area or “dash pot” on the upper ends of control rods absorb energy from dropped control rod assemblies without narrowing the diameter of guide tubes. As a result, coolant can freely flow through the guide tubes reducing boiling water issues. The dampening area reduces a separation distance between an outside surface of the control rod and an inside surface of the guide tubes decelerating the control rods when entering a top end of the guide tubes. In another example, the dampening area may be located on a drive shaft. The dampening area may have a larger diameter than an opening in a drive shaft support member that decelerates the drive shaft when dropped by a drive mechanism.
37 - Construction and mining; installation and repair services
40 - Treatment of materials; recycling, air and water treatment,
42 - Scientific, technological and industrial services, research and design
Goods & Services
(1) Nuclear reactors (1) Management and business consulting services in the field of nuclear energy namely: procurement, namely, purchasing power plant components for others; regulatory submission management, namely, assisting others in preparing and filing applications for new nuclear power plants with governmental regulatory bodies; business consulting services in the field of management of nuclear power plants; business consulting services in the field of management of the design, licensing, operation, maintenance, and decommissioning of nuclear power plants; and business consulting services in the field of operation of nuclear power plants; Providing a website featuring information in the field of nuclear energy, namely, the energy efficiency of nuclear energy; providing a website featuring information on the business operation of nuclear power plants
(2) Consulting services in the field of repair and maintenance of nuclear energy power plants; consulting services in the field of construction of nuclear power plants; consulting services in the field of refueling of nuclear power plants
(3) Providing a website featuring information in the field of nuclear energy, namely, the generation of nuclear energy
(4) Consulting services in the field of design, planning, and implementation in the nature of scientific research and safety testing of nuclear power plants; consulting services in the field of calibrating nuclear power plants; nuclear engineering; Providing a website featuring information in the field of nuclear energy, namely, research in the field of nuclear energy; providing a website featuring information on the design of nuclear power plants; providing a website featuring information on the research, development, design, and testing of nuclear reactors
58.
METHODS OF MANUFACTURING STRUCTURES FROM COATED METAL GRAIN MATERIALS, SUCH AS FOR USE IN NUCLEAR REACTOR SYSTEMS, AND RELATED STRUCTURES AND SYSTEMS
Methods of fabricating structures, such as parts for use in nuclear power generation systems, are described herein. A representative method of fabricating a part for a nuclear reactor system includes coating a plurality of particles of a powder of a first material with a second material, and then pressing and/or heating the coated powder into a monolithic structure. The second material can be substantially solidly insoluble with the first material such that, after pressing and/or heating, the particles of the first material define grains of the monolithic structure and the second material substantially encapsulates the grains in the monolithic structure. The first material can be susceptible to corrosion by a select process, and the second material can be resistant to corrosion by the select process such that the bulk first material of the monolithic structure is resistant to corrosion by the select process.
09 - Scientific and electric apparatus and instruments
11 - Environmental control apparatus
35 - Advertising and business services
37 - Construction and mining; installation and repair services
40 - Treatment of materials; recycling, air and water treatment,
41 - Education, entertainment, sporting and cultural services
42 - Scientific, technological and industrial services, research and design
Goods & Services
Electronic simulators for training plant employees and
operators in a nuclear plant control room; downloadable
training simulation software in the field of operation,
maintenance, refueling, and calibration of nuclear power
plants. Nuclear power plants; energy storage plants; nuclear
reactors; component parts specially adapted for nuclear
reactors. Procurement services, namely, purchasing power plant
components for others; regulatory submission management,
namely, assisting others in preparing and filing
applications for new nuclear power plants with governmental
regulatory bodies. Plant construction, maintenance, and construction project
management and consulting services for businesses relating
to plant construction and maintenance, in the energy
production and transmission sector; consulting services in
the field of repair, maintenance, and refueling of nuclear
energy power plants; consulting services in the field of
construction and implementation in the nature of
installation of nuclear power plants; consulting services
relating to construction, maintenance, and repair of nuclear
power plants and other energy source plants. Provision of information, advice, and consultancy in
relation to the production and generation of energy;
consultancy services relating to energy generation by
nuclear power plants and from other energy sources;
providing information in the field of nuclear energy
generation via a website. Educational services, namely, developing curriculum and
training materials for others in the field of operation,
maintenance, refueling, and calibration of nuclear power
plants; training services in the field of operation,
maintenance, refueling, and calibration of nuclear power
plants; consulting services in the field of training for the
operation, maintenance, refueling, and calibration of
nuclear power plants; simulation-based training services in
the field of operation, maintenance, refueling, and
calibration of nuclear power plants. Technological consulting services in the field of energy
generation; technical consultation in the field of
environmental science, engineering services, design for
others in the field of energy engineering, designing, and
testing of energy products for others; technological
planning and consulting services in the field of reduced
carbon and carbon-free energy resources; consulting services
in the field of design, planning, and implementation in the
nature of scientific research and safety testing of nuclear
power plants and other energy sources in the nature of
alternative energy generation power plants and nuclear
energy power plants; nuclear engineering; designing plant
components and equipment for nuclear power plants; providing
information in the field of nuclear energy research via a
website; providing information on the design of nuclear
power plants via a website; providing information on the
research, development, design, and testing of nuclear
reactors via a website.
60.
Controlling a power output of a nuclear reaction using chemical injection
A nuclear power system includes a reactor vessel that includes a reactor core mounted therein. The reactor core includes nuclear fuel assemblies configured to generate a nuclear fission reaction. The nuclear power system further includes a chemical injection system configured to inject a chemical into the reactor vessel and remove the chemical from the reactor vessel, and a control system communicably coupled to the chemical injection system and configured to control a power output of the nuclear fission reaction. For example, the control system can determine that the power output is greater than an upper value of a range or less than a lower value of the range and, based on the determination, adjust an amount of the chemical injected into or removed from the reactor vessel by the chemical injection system to adjust the power output.
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 7/12 - Means for moving control elements to desired position
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 1/02 - Fast fission reactors, i.e. reactors not using a moderator
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 7/24 - Selection of substances for use as neutron-absorbing material
G21C 9/02 - Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse
G21C 9/027 - Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse by fast movement of a solid, e.g. pebbles
G21C 13/02 - Pressure vesselsContainment vesselsContainment in general Details
Supports with integrated sensors for nuclear reactor steam generators, and associated systems and methods, are disclosed. A representative method for forming a nuclear-powered steam generator includes forming an instrumented support, the instrumented support including a carrier portion and a retainer portion, with at least one of the carrier portion or the retainer portion being integrally formed with a sensor via an additive manufacturing process. The method can further include coupling the sensor to a communication link, supporting a helical steam conduit on the instrumented support, and installing the helical steam conduit and the instrumented support in a nuclear reactor. The helical steam conduit is positioned along a primary flow path, which is in turn positioned to circulate a heated primary flow in thermal communication with the helical steam conduit.
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 nuclear power system includes a reactor vessel that includes a reactor core that includes nuclear fuel assemblies configured to generate a nuclear fission reaction. A representative nuclear power system further includes a riser positioned above there actor core and a primary coolant flow path that extends from a bottom portion of the reactor vessel, through the reactor core, and through an annulus between the riser and the reactor vessel. A primary coolant circulates through the primary coolant flow path to receive heat from the nuclear fission reaction and release the heat to a power generation system configured to generate electric power. The nuclear power system further includes a control rod assembly system positioned in the reactor vessel and configured to position control rods in only two discrete positions.
G21C 7/12 - Means for moving control elements to desired position
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
G21C 1/02 - Fast fission reactors, i.e. reactors not using a moderator
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 7/24 - Selection of substances for use as neutron-absorbing material
G21C 9/02 - Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse
G21C 13/02 - Pressure vesselsContainment vesselsContainment in general Details
Supports with integrated sensors for nuclear reactor steam generators, and associated systems and methods, are disclosed. A representative method for forming a nuclear-powered steam generator includes forming an instrumented support, the instrumented support including a carrier portion and a retainer portion, with at least one of the carrier portion or the retainer portion being integrally formed with a sensor via an additive manufacturing process. The method can further include coupling the sensor to a communication link, supporting a helical steam conduit on the instrumented support, and installing the helical steam conduit and the instrumented support in a nuclear reactor. The helical steam conduit is positioned along a primary flow path, which is in turn positioned to circulate a heated primary flow in thermal communication with the helical steam conduit.
G21C 17/10 - Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
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
F28D 7/02 - Heat-exchange apparatus having stationary tubular conduit assemblies for both heat-exchange media, the media being in contact with different sides of a conduit wall the conduits being helically coiled
F28F 9/00 - CasingsHeader boxesAuxiliary supports for elementsAuxiliary members within casings
09 - Scientific and electric apparatus and instruments
11 - Environmental control apparatus
35 - Advertising and business services
37 - Construction and mining; installation and repair services
40 - Treatment of materials; recycling, air and water treatment,
41 - Education, entertainment, sporting and cultural services
42 - Scientific, technological and industrial services, research and design
Goods & Services
(1) Electronic simulators for training plant employees and operators in a nuclear plant control room; Downloadable training simulation software in the field of operation, maintenance, refueling, and calibration of nuclear power plants.
(2) Energy generation power plants, namely nuclear power plants; nuclear power storage plants; nuclear reactors; component parts specially adapted for nuclear reactors. (1) Procurement services, namely, purchasing power plant components for others, namely purchasing of nuclear reactors, and component parts specifically adapted for nuclear reactors; regulatory submission management, namely, assisting others in preparing and filing applications for new nuclear power plants with governmental regulatory bodies.
(2) Construction and maintenance of electricity plants, construction project management and consulting services for businesses in the energy production and transmission sector; consulting services in the field of repair, maintenance, and refueling of nuclear energy power plants; consulting services in the field of construction and implementation in the nature of installation of nuclear power plants; consulting services in the field of implementation in the nature of energy generation of nuclear power plants, hydroelectric power plants, solar power plants, wind power plants, and electricity plants powered by fossil fuels.
(3) Provision of information, advice, and consultancy in relation to the generation of electricity; consultancy services relating to energy generation by nuclear power plants hydroelectric power plants, solar power plants, wind power plants, and electricity plants powered by fossil fuels; providing information in the field of nuclear energy generation via a website; technological consulting services in the field of generation of electricity.
(4) Educational services, namely, developing curriculum and training materials for others in the field of operation, maintenance, refueling, and calibration of nuclear power plants; Training services in the field of operation, maintenance, refueling, and calibration of nuclear power plants; Consulting services in the field of training for the operation, maintenance, refueling, and calibration of nuclear power plants; Simulation-based training services in the field of operation, maintenance, refueling, and calibration of nuclear power plants.
(5) Technical consultation in the field of environmental science, engineering services, design for others in the field of energy engineering, designing, and testing of energy products for others; technological planning and consulting services in the field of reduced carbon and carbon-free energy resources; consulting services in the field of design, planning, and implementation in the nature of scientific research and safety testing of nuclear power plants and other energy sources in the nature of alternative energy generation power plants and nuclear energy power plants; nuclear engineering; designing plant components and equipment for nuclear power plants; providing a website featuring information in the field of nuclear energy research; providing a website featuring information on the design of nuclear power plants; providing a website featuring information on the research, development, design, and testing of nuclear reactors.
65.
Nuclear reactor plant for housing nuclear reactor modules
An in-core instrumentation system for a reactor module includes a plurality of in-core instruments connected to a containment vessel and a reactor pressure vessel at least partially located within the containment vessel. A reactor core is housed within a lower head that is removably attached to the reactor pressure vessel, and lower ends of the in-core instruments are located within the reactor core. The in-core instruments are configured such that the lower ends are concurrently removed from the reactor core as a result of removing the lower head from the reactor pressure vessel.
G21C 19/32 - Apparatus for removing radioactive objects or materials from the reactor discharge area, e.g. to a storage placeApparatus for handling radioactive objects or materials within a storage place or removing them therefrom
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 1/32 - 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
G21C 13/02 - Pressure vesselsContainment vesselsContainment in general Details
G21C 17/10 - Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
G21C 19/18 - Apparatus for bringing fuel elements to the reactor charge area, e.g. from a storage place
G21C 19/20 - Arrangements for introducing objects into the pressure vesselArrangements for handling objects within the pressure vesselArrangements for removing objects from the pressure vessel
Pressure vessels and closures for pressure vessels, such as for use in nuclear reactor systems, are described herein. A representative pressure vessel includes (i) a first enclosure including a first flange having a lower surface and a first inner surface, and (ii) a second enclosure including a second flange having an upper surface and a second inner surface. The pressure vessel can further include a sealing member having a first portion and a second portion. The first portion is configured to contact both the lower surface of the first flange and the upper surface of the second flange to provide a first seal between the first and second enclosures. The second portion is configured to contact, via an interference fit, both the first inner surface of the first flange and the second inner surface of the second flange to provide a second seal between the first and second enclosures.
Method of fabricating structures, such as parts for use in nuclear power generation systems, are described herein. A representative method of fabricating a part for a nuclear reactor system includes additively manufacturing the part as a monolithic structure from a wire formed of an oxide dispersion strengthen (ODS) material, which includes an oxide material dispersed within a metal material. Specifically, the method can include directing a beam of thermal energy toward the wire to melt the wire, and permitting the melted wire to cool and solidify to form the part such that the oxide material remains substantially dispersed within the metal material. By maintaining the dispersion of the oxide material within the metal material, the ODS material can retain a good creep resistance, wear-resistance, corrosion resistance, and/or other ODS material property at elevated temperatures—even after fabrication.
Power generation systems, such as nuclear power generation systems, are described herein. A representative power generation system includes a heat source, a heat pipe, and a thermophotovoltaic cell. The heat pipe includes a first region and a second region. The first region is positioned to absorb heat from the heat source, and the second region is positioned to radiate at least a portion of the absorbed heat away from the heat pipe as thermal radiation. The thermophotovoltaic cell is positioned to receive the thermal radiation from the second region of the heat pipe and to convert at least a portion of the thermal radiation to electrical energy. The power generation system can further include another heat pipe positioned to remove waste heat from the thermophotovoltaic cell.
F28D 15/02 - Heat-exchange apparatus with the intermediate heat-transfer medium in closed tubes passing into or through the conduit walls in which the medium condenses and evaporates, e.g. heat-pipes
69.
HEAT PIPES INCLUDING COMPOSITE WICKING STRUCTURES, AND ASSOCIATED METHODS OF MANUFACTURE
Heat pipes and methods of forming heat pipes, such as for use in nuclear reactor systems, are described herein. A representative method of forming a heat pipe includes forming a first wicking structure from a first material and forming a second wicking structure on the first wicking structure. Forming the second wicking structure can include mixing a second material and a third material, and heating the mixture of the second material and the third material to a temperature (a) less than a melting temperature of the second material and (b) greater than a melting temperature of the third material to melt the third material. The method can further include cooling the mixture of the second material and the third material to below the melting temperature of the third material such that the third material solidifies to bond together a plurality of particles of the second material into a porous structure.
F28D 15/04 - Heat-exchange apparatus with the intermediate heat-transfer medium in closed tubes passing into or through the conduit walls in which the medium condenses and evaporates, e.g. heat-pipes with tubes having a capillary structure
F16L 11/12 - Hoses, i.e. flexible pipes made of rubber or flexible plastics with arrangements for particular purposes, e.g. specially profiled, with protecting layer, heated, electrically conducting
F16L 11/14 - Hoses, i.e. flexible pipes made of rigid material, e.g. metal or hard plastics
F28F 13/18 - Arrangements for modifying heat transfer, e.g. increasing, decreasing by applying coatings, e.g. radiation-absorbing, radiation-reflectingArrangements for modifying heat transfer, e.g. increasing, decreasing by surface treatment, e.g. polishing
F28F 21/04 - Constructions of heat-exchange apparatus characterised by the selection of particular materials of ceramicConstructions of heat-exchange apparatus characterised by the selection of particular materials of concreteConstructions of heat-exchange apparatus characterised by the selection of particular materials of natural stone
F28F 21/08 - Constructions of heat-exchange apparatus characterised by the selection of particular materials of metal
70.
Thermal power conversion systems including heat pipes and photovoltaic cells
Power generation systems, such as nuclear power generation systems, are described herein. A representative power generation system includes a heat source, a heat pipe, and a thermophotovoltaic cell. The heat pipe includes a first region and a second region. The first region is positioned to absorb heat from the heat source, and the second region is positioned to radiate at least a portion of the absorbed heat away from the heat pipe as thermal radiation. The thermophotovoltaic cell is positioned to receive the thermal radiation from the second region of the heat pipe and to convert at least a portion of the thermal radiation to electrical energy. The power generation system can further include another heat pipe positioned to remove waste heat from the thermophotovoltaic cell.
Heat pipes and methods of forming heat pipes, such as for use in nuclear reactor systems, are described herein. A representative method of forming a heat pipe includes forming a first wicking structure from a first material and forming a second wicking structure on the first wicking structure. Forming the second wicking structure can include mixing a second material and a third material, and heating the mixture of the second material and the third material to a temperature (a) less than a melting temperature of the second material and (b) greater than a melting temperature of the third material to melt the third material. The method can further include cooling the mixture of the second material and the third material to below the melting temperature of the third material such that the third material solidifies to bond together a plurality of particles of the second material into a porous structure.
F28D 15/04 - Heat-exchange apparatus with the intermediate heat-transfer medium in closed tubes passing into or through the conduit walls in which the medium condenses and evaporates, e.g. heat-pipes with tubes having a capillary structure
F28F 21/04 - Constructions of heat-exchange apparatus characterised by the selection of particular materials of ceramicConstructions of heat-exchange apparatus characterised by the selection of particular materials of concreteConstructions of heat-exchange apparatus characterised by the selection of particular materials of natural stone
F28F 21/08 - Constructions of heat-exchange apparatus characterised by the selection of particular materials of metal
G21C 15/257 - Promoting flow of the coolant using heat-pipes
B22F 10/28 - Powder bed fusion, e.g. selective laser melting [SLM] or electron beam melting [EBM]
B28B 1/00 - Producing shaped articles from the material
A damping area or “dash pot” on the upper ends of control rods absorb energy from dropped control rod assemblies without narrowing the diameter of guide tubes. As a result, coolant can freely flow through the guide tubes reducing boiling water issues. The dampening area reduces a separation distance between an outside surface of the control rod and an inside surface of the guide tubes decelerating the control rods when entering a top end of the guide tubes. In another example, the dampening area may be located on a drive shaft. The dampening area may have a larger diameter than an opening in a drive shaft support member that decelerates the drive shaft when dropped by a drive mechanism.
G21C 7/20 - Disposition of shock-absorbing devices
G21C 7/11 - Deformable control elements, e.g. flexible, telescopic, articulated
G21C 7/117 - Clusters of control rodsSpider construction
G21C 3/322 - Means to influence the coolant flow through or around the bundles
G21C 3/33 - Supporting or hanging of elements in the bundleMeans forming part of the bundle for inserting it into, or removing it from, the coreMeans for coupling adjacent bundles
G21C 9/02 - Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse
A thermal control system for a reactor pressure vessel comprises a plate having a substantially circular shape that is attached to a wall of the reactor pressure vessel. The plate divides the reactor pressure vessel into an upper reactor pressure vessel region and a lower reactor pressure vessel region. Additionally, the plate is configured to provide a thermal barrier between a pressurized volume located within the upper reactor pressure vessel region and primary coolant located within the lower reactor pressure vessel region. One or more plenums provide a passageway for a plurality of heat transfer tubes to pass fluid through the wall of the reactor pressure vessel. The plurality of heat transfer tubes are connected to the plate.
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 pressure vesselArrangement 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 13/02 - Pressure vesselsContainment vesselsContainment in general Details
G21C 15/16 - Cooling arrangements within the pressure vessel containing the coreSelection of specific coolants comprising means for separating liquid and steam
F22B 1/02 - Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers
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
A system for servicing a nuclear reactor module comprises a crane operable to attach to the nuclear reactor module, wherein the crane includes provisions for routing signals from one or more sensors of the nuclear reactor module to one or more sensor receivers.
B66C 13/46 - Position indicators for suspended loads or for crane elements
G21C 19/20 - Arrangements for introducing objects into the pressure vesselArrangements for handling objects within the pressure vesselArrangements for removing objects from the pressure vessel
G21C 17/10 - Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
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
B66C 17/06 - Overhead travelling cranes comprising one or more substantially-horizontal girders the ends of which are directly supported by wheels or rollers running on tracks carried by spaced supports specially adapted for particular purposes, e.g. in foundries, forgesOverhead travelling cranes comprising one or more substantially-horizontal girders the ends of which are directly supported by wheels or rollers running on tracks carried by spaced supports combined with auxiliary apparatus serving particular purposes
B66C 13/14 - Arrangements of means for transmitting pneumatic, hydraulic, or electric power to movable parts or devices to load-engaging elements or motors associated therewith
B66C 13/08 - Auxiliary devices for controlling movements of suspended loads, or for preventing cable slack for depositing loads in desired attitudes or positions
B66C 19/00 - Cranes comprising trolleys or crabs running on fixed or movable bridges or gantries
B66C 13/06 - Auxiliary devices for controlling movements of suspended loads, or for preventing cable slack for minimising or preventing longitudinal or transverse swinging of loads
G21C 17/06 - Devices or arrangements for monitoring or testing fuel or fuel elements outside the reactor core, e.g. for burn-up, for contamination
B66C 17/00 - Overhead travelling cranes comprising one or more substantially-horizontal girders the ends of which are directly supported by wheels or rollers running on tracks carried by spaced supports
B66C 13/00 - Other constructional features or details
B66C 17/26 - Overhead travelling cranes comprising one or more substantially-horizontal girders the ends of which are directly supported by wheels or rollers running on tracks carried by spaced supports specially adapted for particular purposes, e.g. in foundries, forgesOverhead travelling cranes comprising one or more substantially-horizontal girders the ends of which are directly supported by wheels or rollers running on tracks carried by spaced supports combined with auxiliary apparatus serving particular purposes combined with auxiliary apparatus, e.g. log saws, pushers for unloading vehicles, means for shunting railway vehicles
A nuclear reactor protection system includes a plurality of functionally independent modules, each of the modules configured to receive a plurality of inputs from a nuclear reactor safety system, and logically determine a safety action based at least in part on the plurality of inputs, each of the functionally independent modules comprising a digital module or a combination digital and analog module, an analog module electrically coupled to one or more of the functionally independent modules, and one or more nuclear reactor safety actuators communicably coupled to the plurality of functionally independent modules to receive the safety action determination based at least in part on the plurality of inputs.
H02H 3/05 - Emergency protective circuit arrangements for automatic disconnection directly responsive to an undesired change from normal electric working condition, with or without subsequent reconnection Details with means for increasing reliability, e.g. redundancy arrangements
77.
Systems and methods for monitoring a power-generation module assembly after a power-generation module shutdown event
Embodiments are directed to providing a user interface (UI) that streamlines and simplifies the process of monitoring critical power-generation module (PGM) parameters after a PGM assembly is shutdown. The UI displays, in real-time, indicators corresponding to one or more post-shutdown PGM parameters. The UI provides indications of whether the post-shutdown PGM parameters meet post-shutdown criteria of the PGM assembly. When a post-shutdown PGM parameter does not meet the post-shutdown criteria, a user alert is provided to the user. A protocol may additionally be provided to the user. In some embodiments, the protocol may enable the user to return the PGM assembly to a condition that satisfies the post-shutdown criteria. The protocol may be a safety protocol and/or an asset protection protocol.
A nuclear reactor protection system includes a plurality of functionally independent modules, each of the modules configured to receive a plurality of inputs from a nuclear reactor safety system, and logically determine a safety action based at least in part on the plurality of inputs; and one or more nuclear reactor safety actuators communicably coupled to the plurality of functionally independent modules to receive the safety action determination based at least in part on the plurality of inputs.
G21D 3/06 - Safety arrangements responsive to faults within the plant
H02H 3/05 - Emergency protective circuit arrangements for automatic disconnection directly responsive to an undesired change from normal electric working condition, with or without subsequent reconnection Details with means for increasing reliability, e.g. redundancy arrangements
79.
Heat pipe networks for heat removal, such as heat removal from nuclear reactors, and associated systems and methods
Nuclear reactor systems and associated devices and methods are described herein. A representative nuclear reactor system includes a heat pipe network having an evaporator region, an adiabatic region, and a condenser region. The heat pipe network can define a plurality of flow paths having an increasing cross-sectional flow area in a direction from the evaporator region toward the condenser region. The system can further include nuclear fuel thermally coupled to at least a portion of the evaporator region. The heat pipe network is positioned to transfer heat received from the fuel at the evaporator region, to the condenser region. The system can further include one or more heat exchangers thermally coupled to the evaporator region for transporting the heat out of the system for use in one or more processes, such as generating electricity.
G21C 15/257 - Promoting flow of the coolant using heat-pipes
F28D 15/02 - Heat-exchange apparatus with the intermediate heat-transfer medium in closed tubes passing into or through the conduit walls in which the medium condenses and evaporates, e.g. heat-pipes
Nuclear reactor systems and associated devices and methods are described herein. A representative nuclear reactor system includes a reactor vessel having a barrier separating a core region from a shield region. A plurality of fuel rods containing a liquid nuclear fuel are positioned in the core region. A liquid moderator material is also positioned in the core region at least partially around the fuel rods. A plurality of heat exchangers can be positioned in the shield region, and a plurality of heat pipes can extend through the barrier. The moderator material is positioned to transfer heat received from the liquid nuclear fuel to the heat pipes, and the heat pipes are positioned to transfer heat received from the moderator material to the heat exchangers. The heat exchangers can transport the heat out of the system for use in one or more processes, such as generating electricity.
G21C 3/24 - Fuel elements with fissile or breeder material in fluid form within a non-active casing
G21C 5/02 - Moderator or core structureSelection of materials for use as moderator Details
G21C 5/12 - Moderator or core structureSelection of materials for use as moderator characterised by composition, e.g. the moderator containing additional substances which ensure improved heat resistance of the moderator
G21C 7/26 - Control of nuclear reaction by displacement of the moderator or parts thereof
G21C 7/02 - Control of nuclear reaction by using self-regulating properties of reactor materials
G21C 11/06 - Reflecting shields, i.e. for minimising loss of neutrons
G21C 15/04 - 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
G21C 15/08 - 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 moderating material
G21C 15/257 - Promoting flow of the coolant using heat-pipes
81.
HEAT PIPE NETWORKS FOR HEAT REMOVAL, SUCH AS HEAT REMOVAL FROM NUCLEAR REACTORS, AND ASSOCIATED SYSTEMS AND METHODS
Nuclear reactor systems and associated devices and methods are described herein. A representative nuclear reactor system includes a heat pipe network having an evaporator region, an adiabatic region, and a condenser region. The heat pipe network can define a plurality of flow paths having an increasing cross-sectional flow area in a direction from the evaporator region toward the condenser region. The system can further include nuclear fuel thermally coupled to at least a portion of the evaporator region. The heat pipe network is positioned to transfer heat received from the fuel at the evaporator region, to the condenser region. The system can further include one or more heat exchangers thermally coupled to the evaporator region for transporting the heat out of the system for use in one or more processes, such as generating electricity.
Nuclear reactor systems and associated devices and methods are described herein. A representative nuclear reactor system includes a reactor vessel having a barrier separating a core region from a shield region. A plurality of fuel rods containing a liquid nuclear fuel are positioned in the core region. A liquid moderator material is also positioned in the core region at least partially around the fuel rods. A plurality of heat exchangers can be positioned in the shield region, and a plurality of heat pipes can extend through the barrier. The moderator material is positioned to transfer heat received from the liquid nuclear fuel to the heat pipes, and the heat pipes are positioned to transfer heat received from the moderator material to the heat exchangers. The heat exchangers can transport the heat out of the system for use in one or more processes, such as generating electricity.
A system for attenuating seismic forces includes a reactor pressure vessel containing nuclear fuel and a containment vessel that houses the reactor pressure vessel. Both the reactor pressure vessel and the containment vessel include a bottom head. Additionally, the system includes a base support to contact a support surface on which the containment vessel is positioned in a substantially vertical orientation. An attenuation device is located between the bottom head of the reactor pressure vessel and the bottom head of the containment vessel. Seismic forces that travel from the base support to the reactor pressure vessel via the containment vessel are attenuated by the attenuation device in a direction that is substantially lateral to the vertical orientation of the containment vessel.
G21C 5/10 - Means for supporting the complete structure
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
G21C 13/024 - Supporting constructions for pressure vessels or containment vessels
A raised face flange assembly comprises an upper flange (11) to couple to a lower flange (12) using one or more bolts (5): wherein the upper flange (11) or the lower flange (12) comprises: a bolting face (25) defining one or more openings for the one or more bolts (5), respectively; a pair of raised faces (21, 22) including a first raised face and a second raised face to make contact with a mating surface of the other of the upper flange (11) or the lower flange (12); wherein a distance between an area of the second raised face (22) and a plane corresponding to the bolting face (25) is greater than a distance between an area of the first raised face (21) and the plane to distribute contact force with a mating surface over the area of the second raised face (22) to maintain a seal.
A cooling system for a nuclear reactor control rod drive mechanism (CRDM) includes an evaporation section located within or next to the CRDM and a condensation section fluidly coupled to the evaporation section. The cooling system may include a set of heat fins that extend up from drive coils in the CRDM and heat pipes that extend through the drive coils and heat fins. A fluid evaporates while in the evaporation section of the heat pipes from heat generated by the CRDM and moves out of the evaporation section into the condensation section in the heat fins. The fluid cools and condensates while in the condensation section, recirculating back into the evaporation section. This passive natural circulation cooling system reduces or eliminates the number of water hoses, piping, and other water pumping equipment typically used for cooling CRDM, or the requirement for air cooling, increasing nuclear reactor reliability and simplifying nuclear reactor operation and maintenance.
G21C 7/12 - Means for moving control elements to desired position
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
G21C 15/257 - Promoting flow of the coolant using heat-pipes
In an example, a raised face flange assembly, comprises an upper flange to couple to a lower flange using one or more bolts: wherein the upper flange or the lower flange comprises: a bolting face defining one or more openings for the one or more bolts, respectively; a pair of raised faces including a first raised face and a second raised face to make contact with a mating surface of the other of the upper flange or the lower flange; wherein a distance between an area of the second raised face and a plane corresponding to the bolting face is greater than a distance between an area of the first raised face and the plane to distribute contact force with a mating surface over the area of the second raised face to maintain a seal.
A nuclear reactor module includes a reactor core and a reactor housing that surrounds the reactor core about its sides, wherein the reactor housing is configured to direct coolant through the reactor core. A neutron reflector is located between the reactor core and the reactor housing, wherein the neutron reflector has a plurality of inlet ports facing the reactor core. The neutron reflector also has a plurality of outlet ports fluidly connected to the inlet ports to direct a portion of the coolant through the neutron reflector.
An in-core instrumentation system for a reactor module includes a plurality of in-core instruments connected to a containment vessel and a reactor pressure vessel at least partially located within the containment vessel. A reactor core is housed within a lower head that is removably attached to the reactor pressure vessel, and lower ends of the in-core instruments are located within the reactor core. The in-core instruments are configured such that the lower ends are concurrently removed from the reactor core as a result of removing the lower head from the reactor pressure vessel.
G21C 19/18 - Apparatus for bringing fuel elements to the reactor charge area, e.g. from a storage place
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
G21C 13/02 - Pressure vesselsContainment vesselsContainment in general Details
G21C 17/10 - Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
G21C 19/32 - Apparatus for removing radioactive objects or materials from the reactor discharge area, e.g. to a storage placeApparatus for handling radioactive objects or materials within a storage place or removing them therefrom
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 19/20 - Arrangements for introducing objects into the pressure vesselArrangements for handling objects within the pressure vesselArrangements for removing objects from the pressure vessel
89.
Control rod drive mechanism with heat pipe cooling
A representative cooling system for a nuclear reactor control rod drive mechanism (CRDM) includes an evaporation section located within or next to the CRDM and a condensation section fluidly coupled to the evaporation section. The cooling system includes a set of heat fins coupled to drive coils in the CRDM and heat pipes that extend through the drive coils and heat fins. A fluid evaporates while in the evaporation section of the heat pipes from heat generated by the CRDM and moves out of the evaporation section into the condensation section in the heat fins. The fluid cools and condensates while in the condensation section, recirculating back into the evaporation section. This passive natural circulation cooling system reduces or eliminates the number of water hoses, piping, and other water pumping equipment typically used for cooling a CRDM thereby increasing nuclear reactor reliability and simplifying nuclear reactor operation and maintenance.
G21C 15/257 - Promoting flow of the coolant using heat-pipes
H02K 9/20 - Arrangements for cooling or ventilating for machines with closed casing and closed-circuit cooling using a liquid cooling medium, e.g. oil wherein the cooling medium vaporises within the machine casing
90.
Controlling a power output of a nuclear reaction without control rods
A nuclear power system includes a reactor vessel that includes a reactor core mounted therein. The reactor core includes nuclear fuel assemblies configured to generate a nuclear fission reaction. The reaction vessel does not include any control rod assemblies therein. The nuclear power system further includes a riser positioned above the reactor core, a primary coolant flow path, a primary coolant that circulates through the primary coolant flow path to receive heat from the nuclear fission reaction and release the received heat to generate electric power in a power generation, and a control system communicably coupled to the power generation system and configured to control a power output of the nuclear fission reaction independent of any control rod assemblies.
G21D 3/18 - Regulation of any parameters in the plant by adjustment of plant external to the reactor only in response to change in reactivity
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
G21C 7/24 - Selection of substances for use as neutron-absorbing material
G21D 5/08 - Reactor and engine not structurally combined with engine working medium heated in a heat exchanger by the reactor coolant
G21C 1/02 - Fast fission reactors, i.e. reactors not using a moderator
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 9/02 - Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse
G21C 13/02 - Pressure vesselsContainment vesselsContainment in general Details
91.
Boron injection system for controlling a nuclear reaction by delivering boron into a containment vessel
A nuclear power system includes a reactor vessel that includes a reactor core mounted within a volume of the reactor vessel. The reactor core includes one or more nuclear fuel assemblies configured to generate a nuclear fission reaction. The nuclear power system further includes a containment vessel sized to enclose the reactor vessel such that an open volume is defined between the containment vessel and the reactor vessel. A boron injection system is positioned in the open volume of the containment vessel and includes an amount of boron sufficient to stop the nuclear fission reaction or maintain the nuclear fission reaction at a sub-critical state. The boron injection system is positioned to deliver the amount of boron into the open volume.
G21C 9/02 - Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse
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
G21C 9/027 - Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse by fast movement of a solid, e.g. pebbles
G21D 3/18 - Regulation of any parameters in the plant by adjustment of plant external to the reactor only in response to change in reactivity
G21D 5/08 - Reactor and engine not structurally combined with engine working medium heated in a heat exchanger by the reactor coolant
G21C 1/02 - Fast fission reactors, i.e. reactors not using a moderator
G21C 7/12 - Means for moving control elements to desired position
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 13/02 - Pressure vesselsContainment vesselsContainment in general Details
92.
Controlling a power output of a nuclear reaction without control rods
A nuclear power system includes a reactor vessel that includes a reactor core that includes nuclear fuel assemblies configured to generate a nuclear fission reaction. A representative nuclear power system further includes a riser positioned above the reactor core and a primary coolant flow path that extends from a bottom portion of the reactor vessel, through the reactor core, and through an annulus between the riser and the reactor vessel. A primary coolant circulates through the primary coolant flow path to receive heat from the nuclear fission reaction and release the heat to a power generation system configured to generate electric power. The nuclear power system further includes a control rod assembly system positioned in the reactor vessel and configured to position control rods in only two discrete positions.
G21D 3/18 - Regulation of any parameters in the plant by adjustment of plant external to the reactor only in response to change in reactivity
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
G21D 5/08 - Reactor and engine not structurally combined with engine working medium heated in a heat exchanger by the reactor coolant
G21C 1/02 - Fast fission reactors, i.e. reactors not using a moderator
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 9/02 - Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse
G21C 13/02 - Pressure vesselsContainment vesselsContainment in general Details
93.
Systems and methods for monitoring a power-generation module assembly after a power-generation module shutdown event
Embodiments are directed to providing a user interface (UI) that streamlines and simplifies the process of monitoring critical power-generation module (PGM) parameters after a PGM assembly is shutdown. The UI displays, in real-time, indicators corresponding to one or more post-shutdown PGM parameters. The UI provides indications of whether the post-shutdown PGM parameters meet post-shutdown criteria of the PGM assembly. When a post-shutdown PGM parameter does not meet the post-shutdown criteria, a user alert is provided to the user. A protocol may additionally be provided to the user. In some embodiments, the protocol may enable the user to return the PGM assembly to a condition that satisfies the post-shutdown criteria. The protocol may be a safety protocol and/or an asset protection protocol.
An inadvertent actuation block valve includes inlet and outlet orifices being in selective fluid communication via a chamber. A disc is disposed within the chamber and a bellows is configured to contract at a predetermined pressure differential between reactor fluid entering a reference pressure orifice and control fluid entering the inlet orifice. When the bellows contracts, the disc engages the outlet orifice and isolates fluid communication between the inlet and outlet orifices. The inadvertent actuation block valve prevents inadvertent opening of an emergency core cooling valve when a reactor is at operating pressure that is above the predetermined set pressure range. The inadvertent actuation block valve permits the emergency cooling valves to open and to remain open when reactor pressure is below the predetermined set pressure range. The inadvertent actuation block valve does not impede long term emergency cooling that occurs when the reactor is at low pressure.
F15B 20/00 - Safety arrangements for fluid actuator systemsApplications of safety devices in fluid actuator systemsEmergency measures for fluid actuator systems
F16K 17/08 - Safety valvesEqualising valves opening on surplus pressure on one sideSafety valvesEqualising valves closing on insufficient pressure on one side spring-loaded with special arrangements for providing a large discharge passage
F16K 17/04 - Safety valvesEqualising valves opening on surplus pressure on one sideSafety valvesEqualising valves closing on insufficient pressure on one side spring-loaded
F16K 17/10 - Safety valvesEqualising valves opening on surplus pressure on one sideSafety valvesEqualising valves closing on insufficient pressure on one side spring-loaded with auxiliary valve for fluid operation of the main valve
A neutron detection system may include a neutron detection device located outside of a reactor vessel. The neutron detection device may be configured to detect neutrons generated within the reactor vessel. A containment region located intermediate the reactor vessel and a containment vessel may be configured to house a containment medium. A neutron path device may be at least partially located between the reactor vessel and the containment vessel, and the neutron path device may be configured to provide a neutron path to the neutron detection device through a neutron path medium contained within the neutron path device. A neutron attenuation coefficient associated with the neutron path medium may be smaller than a neutron attenuation coefficient associated with the containment medium.
G01N 23/05 - Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups , or by transmitting the radiation through the material and forming images of the material using neutrons
Implementations of a nuclear reactor system include a passive boron injection system operable to release an amount of boron into a containment vessel sufficient to shut down a nuclear fission reaction or maintain the nuclear fission reaction in a sub-critical state. Implementations of a nuclear reactor system include a reactor module that is free of any control rod assemblies. Implementations of a nuclear reactor system include a reactor module that includes a control rod assembly system that is operable to position control rod assemblies in only two discrete positions.
97.
Nuclear reactor module with a cooling chamber for a drive motor of a control rod drive mechanism
In some embodiments, a nuclear reactor vessel comprises a containment vessel for a reactor pressure vessel (RPV); a control rod drive mechanism (CRDM) located in the containment vessel, the CRDM including drive motors configured to move control rods into and out of a nuclear reactor core located in the RPV; and a partition extending across a portion of the containment vessel configured to retain the drive motors in a separate fluid-tight barrier region within the containment vessel. Other embodiments may be disclosed and/or claimed.
G21C 13/04 - Arrangements for expansion and contraction
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
In some embodiments, a nuclear reactor vessel comprises a containment vessel for a reactor pressure vessel (RPV); a control rod drive mechanism (CRDM) located in the containment vessel, the CRDM including drive motors configured to move control rods into and out of a nuclear reactor core located in the RPV; and a partition extending across a portion of the containment vessel configured to retain the drive motors in a separate fluid-tight barrier region within the containment vessel. Other embodiments may be disclosed and/or claimed.
G21C 7/12 - Means for moving control elements to desired position
G21C 13/04 - Arrangements for expansion and contraction
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 method of creating a computer-generated model of a portion of a nuclear reactor that is positioned between an emitter and a detector of an imaging device. The method includes transmitting energy by the detector emitter toward the containment vessel; receiving at the detector at least a portion of the energy transmitted by the emitter, the at least a portion of the energy being attenuated by a tracing agent in a tube sheet or scattered by the tubesheet of the nuclear reactor within the containment vessel; and creating a computer-generated model of the tubesheet based on the at least a portion of the energy received at the detector, the computer-generated model comprising one or more 3D images of the tubesheet.
A nuclear reactor seismic isolation assembly includes an enclosure that defines a volume; a plastically-deformable member mounted, at least in part, within the volume; and a stretching member moveable within the enclosure to plastically-deform the plastically-deformable member in response to a dynamic force exerted on the enclosure.
G21C 13/024 - Supporting constructions for pressure vessels or containment vessels
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 9/00 - Emergency protection arrangements structurally associated with the reactor
G21C 13/032 - Joints between tubes and vessel walls, e.g. taking into account thermal stresses
G21C 13/04 - Arrangements for expansion and contraction
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
F16F 7/12 - Vibration-dampersShock-absorbers using plastic deformation of members
E04H 9/00 - 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
