285results about "Integral reactors" patented technology

An integral molten salt nuclear reactor includes a drain tank section configured to hold a volume of fuel salt. The integral molten salt nuclear reactor further includes a reactor section configured to receive the volume of fuel salt from the drain tank and cause fission reactions that heats the molten salt. The integral molten salt nuclear reactor further includes a heat exchange section configured to receive a flow of the heated fuel salt from the reactor section and remove heat therefrom.

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).

A reactor body structure and a reactor system. The reactor body structure (100) comprises: a reactor pressure vessel (1), the reactor pressure vessel (1) comprising a bottom closure head (3), and the bottom closure head (3) having an arc-shaped inner wall (32); a reactor internal (2), the reactor internal (2) comprising a reactor core supporting lower plate (22); and a reactor core (21), the reactor core (21) being arranged on the reactor core supporting lower plate (22); wherein the reactor core supporting lower plate (22) is located on the lower side of the center of sphere of the arc-shaped inner wall (32), and the outer edge of the reactor core supporting lower plate (22) is provided with a flow guide corner (221); the reactor core supporting lower plate (22) is provided with through holes (222), the through holes (222) are stepped holes and each comprise a top hole (222a) in the upper side and a bottom hole (222b) in the lower side, and the diameter of the bottom hole (222b) is smaller than that of the top hole (222a).

Embodiments of the present disclosure include an integral nuclear reactor having a core fluidly coupled to an inlet chamber and to an outlet chamber. In some instances, the nuclear reactor may include a hub to house the core, the chambers, and the protective plug. The hub may include a window allowing a heat transfer fluid to flow from the outlet chamber, through the hub, and enter an annular space between the hub and a separation shell. The heat transfer fluid may flow into an inlet of a heat exchanger. The heat transfer fluid may flow through the heat exchanger before exiting at a heat exchanger outlet. The heat transfer fluid may enter an annular delay tank before flowing down an annular downcomer duct formed by the separation shell being housed in a reactor vessel. The heat transfer fluid may flow from the annular downcomer duct and into the inlet chamber.

The invention relates to the technical field of lead-based stacks, in particular to a nuclear storage integrated lead-based stack with a load autonomous following function. The nuclear storage integrated lead-based reactor with the automatic load following function comprises a reactor core, a phase change energy storage device and a heat energy utilization device, the reactor core is used for heating a coolant; the heat energy utilization device is used for absorbing heat in the coolant; the phase change energy storage device is arranged on the inlet side of the reactor core, the phase change energy storage device is used for carrying out heat interaction with a coolant, and the phase change temperature of the phase change energy storage device is consistent with the preset inlet temperature of the reactor core. According to the nuclear storage integrated lead-based reactor with the automatic load following function, natural circulation flow is not prone to oscillation and diffusion, the risk of overheating melting of the fuel assembly is not prone to occurring, thermal fatigue of the structural assembly is not prone to occurring, and high safety performance is achieved.

A flattened temperature reactor core structure comprises a fuel assembly, and the fuel assembly comprises a base body, a fuel rod and a heat pipe. Wherein a plurality of mounting holes extending in the axial direction of the base body are formed in the axial section of the base body, the mounting holes are arranged in multiple parallel columns in the first direction, the mounting holes in the second direction forming a 60-degree included angle with the first direction are also arranged in columns, and the mounting holes arranged along the edge of the base body have the same minimum distance with the edge. Two fuel rods are arranged between every two heat pipes in the first direction and the second direction; and in the fuel rods arranged along the edge of the base body, one of two adjacent fuel rods is replaced by a vacant position. And the plurality of fuel assemblies are densely laid to form a reactor core structure. According to the reactor core structure, temperature flattening can be effectively achieved, local overheating is avoided, and therefore the efficiency and reliability of the heat pipe micro-reactor are improved. The invention also provides a heat pipe micro-stack.

A containment system for an integral molten salt reactor includes a sealed containment structure defining a containment volume. The containment structure includes a fission product adsorbing / absorbing material. The containment system further includes an integral molten salt reactor housed fully within the containment volume of the sealed containment structure. The integral molten salt reactor may permit circulation of a fuel salt therein being heated by fission reactions, and allow for the export of heat from said fuel salt.

A containment system for an integral molten salt reactor includes a sealed containment structure defining a containment volume. The containment structure includes a fission product adsorbing / absorbing material. The containment system further includes an integral molten salt reactor housed fully within the containment volume of the sealed containment structure. The integral molten salt reactor may permit circulation of a fuel salt therein being heated by fission reactions, and allow for the export of heat from said fuel salt.

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.

The invention discloses a vehicle-mounted heat pipe reactor start-stop auxiliary device and a start-stop control method. The vehicle-mounted heat pipe reactor start-stop auxiliary device comprises a vehicle power system, a high-temperature and high-pressure gas container and a heat storage system, and can control three states of vehicle driving and starting the reactor, vehicle stopping and stopping the reactor, and vehicle driving and the heat pipe reactor cannot operate normally. Through the sequence of driver behavior-heat pipe reactor start-stop-vehicle start-stop, an intelligent start-stop auxiliary device and a start-stop control method combining the vehicle and the heat pipe reactor are formed; the vehicle-mounted heat pipe reactor provides power for the vehicle carried, and is combined with an internal combustion engine to provide double insurance for driving; the invention has the advantages of improving the mobile operation capability of the vehicle-mounted heat pipe reactor under potentially destructive transportation conditions or harsh operating environments, facilitating the rapid deployment of the reactor to disaster areas, remote areas, extremely cold areas, etc., so that the vehicle-mounted heat pipe reactor has higher safety, reliability and environmental protection, and achieves the purpose of energy saving and emission reduction.

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.

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).

A nuclear reactor is configured with a primary coolant loop for transferring heat away from the nuclear reactor core. In a shutdown event, the primary coolant pump may stop pumping primary coolant through the reactor core, resulting in decay heat buildup within the reactor core. An inertial energy coast down system can store kinetic energy while the nuclear reactor is operating and then release the stored kinetic energy to cause the primary coolant to continue to flow through the nuclear reactor core to remove decay heat. The inertial energy coast down system may include an impeller and a flywheel having a mass. During normal reactor operation, the flowing primary coolant spins up the impeller and flywheel, and upon a shutdown event where the primary coolant pump stops pumping, the flywheel and impeller can cause the primary coolant to continue to flow during a coast down of the flywheel and impeller.

A small-scale nuclear reactor cooling device and a cooling method are provided. The small-scale nuclear reactor cooling device includes a reactor vessel in which cooling water circulates along a flow path structure, and a cooling water storage unit that is provided inside the reactor vessel and is filled with the cooling water based on the circulating flow, and when a molten core occurs in the reactor vessel due to the occurrence of a serious accident, the cooling water storage unit comes into contact with the molten core via the cooling water filled inside to cool the molten core and prevent the molten core from leaking out to the outside.

A containment system for an integral molten salt reactor includes a sealed containment structure defining a containment volume. The containment structure includes a fission product adsorbing / absorbing material. The containment system further includes an integral molten salt reactor housed fully within the containment volume of the sealed containment structure. The integral molten salt reactor may permit circulation of a fuel salt therein being heated by fission reactions, and allow for the export of heat from said fuel salt.

A deployment system for a molten salt reactor includes a reactor module, a cooling module, a coolant preparation module, a fuel shipping module, and a fuel preparation module. Each of the reactor module, the cooling module, the coolant preparation module, the fuel shipping module, and the fuel preparation module may be supplied to a deployment site. Using the coolant preparation module, a coolant salt held within the reactor module may be transferred to the cooling module. Using the fuel preparation module, a fuel salt held within the fuel shipping module may be transferred to the reactor module.

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.

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.

An integral molten salt nuclear reactor includes a drain tank section configured to hold a volume of fuel salt. The integral molten salt nuclear reactor further includes a reactor section configured to receive the volume of fuel salt from the drain tank and cause fission reactions that heats the molten salt. The integral molten salt nuclear reactor further includes a heat exchange section configured to receive a flow of the heated fuel salt from the reactor section and remove heat therefrom.

A nuclear reactor is designed to couple the load path of the control elements with the reactor core, thus reducing the opportunity for differential movement between the control elements and the reactor core. A cartridge core barrel can be fabricated in a manufacturing facility to include the reactor core, control element supports, and control element drive system. The cartridge core barrel can be mounted to a reactor vessel head, and any movement, such as through seismic forces, transmits an equal direction and magnitude to the control elements and the reactor core, thus inhibiting the opportunity for differential movement.

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).

The invention relates to a nuclear reactor provided with a nuclear core (6), arranged on a support (6a) in a bottom of a cylindrical vessel (9) oriented along a vertical axis, filled with a heat-transfer liquid, in particular water, under an upper dome of the vessel, comprising an annular primary exchanger (91) surrounding a flue (9a) for installing and extracting the core, the exchanger starting above the core, extending along the cylindrical wall of the vessel under the dome, and comprising a primary circuit consisting of the heat-transfer liquid circulating in the core and in the primary exchanger by convection, for which a first part of the cylindrical wall (94) of the vessel (9) is surrounded by a first annular casing (1a) forming a cold plenum (83) in communication with an inlet (91a) of a secondary circuit of the exchanger (91) in the lower part of the exchanger and extending from the bottom of the vessel to below an outlet (91b) of the primary exchanger. A second part of the cylindrical wall is surrounded by a second annular casing (1b), above the first annular casing (1a), forming a hot plenum in communication with the outlet (91b) of the secondary circuit of the exchanger (91) in the upper part of the exchanger, an intermediate heat extraction circuit comprising a first pipe (81), for the inflow of cold heat-transfer liquid, opening out in the upper part of the first casing (1a), while a second starting pipe for hot heat-transfer liquid exits in the upper part of the second casing (1b).

The invention provides a heat pipe reactor system and a use method thereof, and the system comprises a heat pipe reactor core, a heat pipe, a main heat exchanger and a thermoelectric conversion system; evaporation sections of the heat pipes are inserted into the heat pipe reactor core, condensation sections of the heat pipes are inserted into the main heat exchanger, and the thermoelectric conversion system is connected with the main heat exchanger; the main heat exchanger comprises a main heat transmission air inlet, a main heat transmission air outlet, a waste heat discharging air inlet and a waste heat discharging air outlet. When the heat pipe reactor normally operates, the waste heat discharge air inlet and the waste heat discharge air outlet are configured to be closed, and the main heat transmission air inlet and the main heat transmission air outlet are configured to be opened to take away heat of the reactor core; and under normal start-stop and accident conditions, the main heat transfer air inlet and the main heat transfer air outlet are configured to be closed, and the waste heat discharge air inlet and the waste heat discharge air outlet are configured to be opened to take away the residual heat of the reactor core.

The present invention relates to a nuclear power plant with improved steam explosion mitigation performance, the nuclear power plant comprising: an integrated reactor including a hemispherical first portion inside which a core and a steam generator are positioned and a cylindrical second portion positioned above the first portion; a containment vessel for accommodating the integrated reactor, having a cooling space surrounding the integrated reactor, and including a first containment portion facing the first portion and a second containment portion facing the second portion; and a lower structure which is located in the cooling space and is located under the integrated reactor, wherein the lower structure comprises a first plate and a second plate disposed below the first plate, and the first plate and the second plate are arranged in a horizontal direction and face each other.

A nuclear power plant comprising at least one nuclear reactor having a steam generator, a steam cycle including the steam generator, a first turbine fluidly coupled to the steam generator, a first condenser fluidly coupled to the first turbine, and a feedwater heater fluidly coupled to the first condenser and the steam generator, an intermediate thermal loop including the first condenser, and an evaporator, and an organic cycle including the evaporator, a second turbine fluidly coupled to the evaporator, a second condenser fluidly coupled to the second turbine, and a heat exchanger fluidly coupled to the second condenser and the evaporator.

Several claimed embodiments of an integrated nuclear reactor relate to nuclear engineering and can be used in reactor systems using several different types of liquid coolants with high boiling points, such as liquid metals, molten salts, and the like. The structural features of the claimed embodiments of the invention, which utilize a spiral heat exchanger segmented along a secondary coolant circuit, provide an improvement in cost-performance by reducing the reactor's metal consumption; efficiently utilizing the reactor's internal volume; improving safety in the event of a leak in the heat exchanger's piping; and providing the ability to remove residual heat after shield plugs are removed before fuel is discharged.

A masking element with an opening is disposed on the side of a core support structure. A flow stack wall defines a plurality of inlets. At least one inlet aligns with the masking element opening when the flow stack is mated with the masking element. A flow control assembly within the flow stack is configured to restrict flow of fluid within the flow stack.

The present invention relates to a nuclear power plant considering defense-in-depth levels, comprising: a plurality of reactors; common facilities that are jointly used by the plurality of reactors; and a measurement control system including a plurality of measurement control platforms corresponding to various operating conditions, wherein the measurement control system separately measures and controls the respective reactors and the common facilities.

A nuclear reactor is designed to couple the load path of the control elements with the reactor core, thus reducing the opportunity for differential movement between the control elements and the reactor core. A cartridge core barrel can be fabricated in a manufacturing facility to include the reactor core, control element supports, and control element drive system. The cartridge core barrel can be mounted to a reactor vessel head. Thus, any movement, such as through seismic forces, transmits an equal direction and magnitude to the control elements and the reactor core. This arrangement reduces the opportunity for differential movement between the control elements and the reactor core.

The application discloses a kind of efficient supercritical carbon dioxide high temperature gas cooled reactor systems and its operating method, the system includes pre-cooler, main compressor, re-compressor, high temperature turbine, low temperature regenerator, high temperature regenerator, high temperature helium-supercritical carbon dioxide heat exchanger, low temperature helium-supercritical carbon dioxide heat exchanger and reactor.The application proposes the power generation system of two-stage split supercritical carbon dioxide cycle comprising high-temperature split re-compression cycle loop and low-temperature re-split reheat expansion cycle loop, by arranging high-temperature helium-supercritical carbon dioxide heat exchanger and low-temperature helium-supercritical carbon dioxide heat exchanger in power generation system, ensure the good matching of helium loop heat release temperature window and supercritical carbon dioxide power cycle loop heat absorption temperature window, realize the efficient cascade utilization of high-temperature gas cooled reactor helium loop large-span temperature interval heat.