189results about "Integral reactors" patented technology

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 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.

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 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.

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.

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 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.

A nuclear installation comprising at least one modular nuclear reactor (SMR) and a reactor vessel well delimiting a water basin in which the SMR reactor unit is immersed. The invention relates to a nuclear installation comprising: at least one SMR reactor unit (4) for heat generation, delimited by a reactor vessel (40, 41, 42); a reactor vessel well (100) delimiting a water-filled basin (B) forming part of a secondary circuit, in which the reactor vessel is immersed; at least one heat exchanger (49) between the primary circuit of the SMR reactor and the secondary circuit, arranged outside the reactor vessel and in the water basin. Figure for the abstract: Fig. 6

Cogeneration installation with a nuclear reactor site and an industrial site with a chemical production unit, the industrial and nuclear sites being separated and connected by a closed-loop thermal energy storage system. The invention essentially consists of physically relocating and functionally separating a nuclear site from an industrial site comprising at least one chemical production unit that utilizes the heat produced by a reactor block at the nuclear site. This physical relocation is achieved by a thermal storage loop with hot and cold tanks located both at the nuclear site and at the industrial site. Figure for the abstract: Fig. 1

Method for renovating a nuclear power plant initially comprising at least one light water nuclear reactor (LWR), in particular a pressurized water reactor (PWR) or boiling water reactor (BWR), replaced by at least one integrated modular nuclear reactor (SMR). The invention essentially consists of a method for retrofitting a nuclear power plant which consists of removing and removing all the components of the primary circuit with the exception of the LWR reactor vessel, which is emptied of all material and neutralized, then replacing in place of a part of these components with sub-assemblies each consisting of an integrated SMR reactor and a mixed concrete / metal structure which acts both as a reactor vessel for the SMR reactor, advantageously filled with water, as an anchor for the SMR inside the reactor building and advantageously as a contribution to the third containment barrier, while minimally modifying the infrastructure of the reactor building. Figure for abstract: Fig. 14D

A curvilinear electromagnetic pump is configured to follow a curve, such as by joining together multiple linear pump segments offset at an angle relative to one another. A curvilinear electromagnetic pump can be curved in two dimensions or in three dimensions. A curvilinear electromagnetic pump allows for more efficient placement of components and systems within a reactor vessel, significantly reducing the height of the reactor vessel compared to vertically positioned linear pumps. A curvilinear electromagnetic pump can follow the curvature of the reactor vessel wall and can be positioned generally near the bottom of the reactor vessel.

A buoyancy driven fluid system coupled to a reactor system configured to achieve free convection operable to cool the reactor system is disclosed. The buoyancy driven fluid system of the present disclosure generates natural circulation by designing the reactor system to have a large vertical offset between the heat exchanger and the reactor core thereby generating a large buoyancy force between a thermal center of the reactor core and a thermal center of the heat exchanger. By ensuring that the sum pressure drop of the components connected to the primary fluid loop is no greater than the buoyancy force of the system, the fluid may circulate throughout the reactor system without the aid of pumps or other forced flow mechanism. The reactor system may be designed within certain size constraints to maintain a compact form while still providing free convection.

To provide a small modular reactor cooling device and cooling method.SOLUTION: A small modular reactor cooling device 100 comprises: a reactor vessel 110 in which a coolant circulates along a flow path structure; and a coolant storage unit provided inside the reactor vessel and charged with the coolant inside based on a circulating flow. Therein when a core melted material is generated in the reactor vessel in an event of a serious accident, the coolant storage unit 140 comes into contact with the core melted material via the coolant charged therein and performs a cooling treatment on the core melted material to prevent the core melted material from leaking outside.SELECTED DRAWING: Figure 1

According to one aspect of the present disclosure, there is provided a manifold (1100) for a heat exchanger assembly (1000) of a nuclear reactor (1) The manifold comprises a peripheral housing (1110), which defines, at least in part, a central volume (1300) for accepting at least one heat exchanger unit (1200) and comprises at least one port (1116, 1118), which communicates with the central volume (1300). A working fluid flow channel (1400) is formed at least in part into the housing (1110). The working fluid flow channel (1400) comprises a collector channel section (1403), which extends along the housing (1110), and at least one inlet channel section (1401), which connects a corresponding at least one port (1116, 1118) to the collector channel section (1403). The manifold also comprises a passage for connecting the collector channel section (1403) to a secondary circuit

A nuclear reactor system includes a drillhole that extends from a terranean surface through one or more subterranean formations; a reactor core positioned in the drillhole, the reactor core comprising at least one nuclear fuel element; a primary coolant system configured to transport a primary fluid coolant between the reactor core and a heat exchanger; and a secondary coolant system thermally coupled to the primary coolant system with the heat exchanger and configured to transport a secondary fluid coolant between the heat exchanger and the terranean surface.

Heat pipe fuel element includes an evaporation section, a condensing section, a capillary section connecting the evaporation section to the condensing section, and a primary coolant. In a cross-section in a plane perpendicular to a longitudinal axis of the evaporation section, the heat pipe fuel element includes a cladding layer enclosing an interior area including a fuel body formed of a fissionable fuel composition and that has an outer surface oriented toward the cladding layer and an inner surface defining a periphery of a vaporization space of the evaporation section. The fuel body has a structure with a shape corresponding to a mathematically-based periodic solid, such as a triply periodic minimal surface (TPMS), and the evaporation sections of a plurality of heat pipe fuel elements are arranged in a phyllotaxis pattern (as seen in a cross-section in a plane perpendicular to a longitudinal axis of the active core region).

The present invention relates to a nuclear reactor, comprising a reactor vessel, a heat exchange device, a drive device, and a water supply device. The reactor vessel contains liquid coolant and an air cavity. The heat exchange device is disposed within the reactor vessel, wherein the inner wall forms a first cavity for accommodating a core, and the outer and inner walls together define a second cavity. One end of the drive device is connected to the air cavity, and the other end is disposed near the core. The water supply device is in communication with the second cavity. When the nuclear reactor is operating normally, the drive device causes the average density of the liquid coolant above the top of the core to be lower than the average density of the lower cavity below the core, thereby generating a gravity difference that drives the liquid coolant to circulate within the reactor vessel, transferring heat generated by the core. When the nuclear reactor malfunctions, the circulating cold source water in the water supply device circulates in the second cavity, continuously exchanging heat with the core to remove excess heat from the core. The present invention eliminates the need for a large main pump, reduces costs, and improves the safety and reliability of the nuclear reactor.

Disclosed is an energy-independent smart port system using SMR-based surplus power. When an SMR-powered vessel docks at a port while the reactor is in operation, the energy-independent smart port system uses relevant technology and equipment to supply surplus power from the SMR-powered vessel to the port in consideration of safety regulations and the characteristic that restarting the reactor of the SMR-powered vessel requires significant time and cost, stably increase the energy independence of a smart port, and can reduce marine air pollutant emissions.

The invention discloses a vehicle-mounted reactor, and relates to the technical field of nuclear reaction, the vehicle-mounted reactor comprises a sealed pressure chamber, a reactor and a residual discharge system, the reactor is arranged in the sealed pressure chamber; the sealed pressure compartment is connected with the reactor through the residual discharge system; and the residual discharge system exchanges heat with the reactor and exchanges heat with the sealed pressure compartment. The vehicle-mounted reactor solves the technical problems that in the prior art, a vehicle-mounted reactor is complex in heat discharge design, breaks down, large in overall reactor mass and the like, and the vehicle-mounted reactor which is small in size and capable of discharging waste heat in the vehicle moving process is provided.