538results about "Heterogenous 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.

The present invention is directed to a fission product extraction system operable to capture and extract fission products from a flow of irradiated fueled molten salt of a molten salt reactor. The example extraction systems described herein utilize electroless deposition to chemically plate fission products onto a metallic structure. The metallic structure may be partially coated with a reducing agent, such as beryllium to provide an electron source for the fission products. The metallic structure may be a component of an extraction system designed to facilitate submersion of the metallic structure into the flow of molten salt. The extraction system may also be designed to facilitate removal of the metallic structure without requiring a shut down or slowdown of the reactor system.

A control method and system for controlling a nuclear power plant includes, in the absence of detection of an imbalance between a primary power signal (S1) and a secondary power signal (S2), the implementation of a setpoint-following mode. The nuclear power plant is controlled as a function of an operational power setpoint (COP), and in the event of detection of an imbalance, automatically implementing a power-limiting mode, including the calculation of a target equilibrium power (PEC) less than or equal to the primary power (P1) and less than or equal to the secondary power (P2), and controlling the nuclear power plant (2) as a function of the target equilibrium power (PEC).

A loading system for a molten salt reactor system includes a slug loading assembly. The slug loading assembly includes an inert chamber having an entry port therein that is configured to receive a solid slug. The loading system further includes a chute having a pipe run extending from the entry port and elevationally below the slug loading assembly. The loading system further includes a terminal sieve fluidically coupled with the pipe run opposite the entry port and configured to receive the solid slug via the pipe run. The terminal sieve is positionable with a flow of a liquid molten salt for dissolution of the solid slug therein.

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.

A mixed-spectrum molten-salt reactor has a primary containment vessel. A reactor core is housed in the primary containment vessel, the reactor core has an atypical geometry that holds a fuel salt. A blanket region is formed within the primary containment vessel and surrounding the reactor core, the blanket region comprises a blanket salt.

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.

A nuclear reactor having an axially stratified fuel bed. The reactor features a reactor housing having a base, a top with an exhaust port, and a shaft. An axially stratified fuel bed within a reactor housing comprising: a first zone configured to operate at a first temperature T1, the first zone comprising a plurality of first fuel pellets, each first fuel pellet comprising a first radioactive ceramic core and a first ceramic seal coating; a second zone configured to operate at a second temperature T2, wherein T2gt; t1, the second zone comprising a plurality of second fuel particles, each second fuel particle comprising a second radioactive ceramic core and a second ceramic sealing coating. A coolant fluid flow path delivers coolant fluid from the reactor base to the vent, sequentially through the first and second zones along the flow path. The stability of the first ceramic sealing coating in T1 is greater than the stability in T2, and the stability of the second ceramic sealing coating in T2 is greater than the stability of the first ceramic sealing coating in T2.

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.

Targetry coupled separation refers to enhancing the production of a predetermined radiation product through the selection of a target (including selection of the target material and the material's physical structure) and separation chemistry in order to optimize the recovery of the predetermined radiation product. This disclosure describes systems and methods for creating (through irradiation) and removing one or more desired radioisotopes from a target and further describes systems and methods that allow the same target to undergo multiple irradiations and separation operations without damage to the target. In contrast with the prior art that requires complete dissolution or destruction of a target before recovery of any irradiation products, the repeated reuse of the same physical target allowed by targetry coupled separation represents a significant increase in efficiency and decrease in cost over the prior art.

A method includes: during a first time period, pumping propellant: to a set of moderator coolant channels to cool the moderator; through a set of fuel elements to heat the propellant to a first outlet temperature; out of a thrust nozzle to produce a first thrust; and locating the reflector at a first closed position to reflect neutrons toward the set of fuel elements to maintain a fission rate of the set of fuel elements above a threshold fission rate. Additionally, during a second time period: locating the reflector at a second open position to reduce the fission rate of the set of fuel elements to below the threshold fission rate; and pumping the propellant through the fuel elements to heat the propellant to a second outlet temperature less than the first outlet temperature and out of the thrust nozzle to produce a second thrust less than the first thrust.

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 fuel assembly (100) for a nuclear fission reactor system (110). The fuel assembly (100) may comprise a pressure tube (120) comprising an aluminium or aluminium alloy. The fuel assembly (100) may comprise a sleeve member (132), the sleeve member (132) extending along a radially inner surface (134) of the pressure tube (120). The fuel assembly (100) may comprise a fuel compact unit (136). The fuel compact unit (136) may be located within the sleeve member (132)) such that a clearance is maintained between a radially inner surface (139) of the sleeve member (132) and the fuel compact unit (136) to define a sleeve member flow passage (140).

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.

The present invention relates to a reactor construction (1) comprising an upper compartment (2) above a drain tank compartment (3), said upper compartment (2) comprising: a molten salt reactor (MSR) (4), comprising a reactor vessel (5) comprising a molten fuel salt (6); a molten salt drain system connected to the reactor vessel (5); said drain tank compartment (3) comprising: one or more drain tanks (10) in communication with the molten salt drain system; a buffer water tank (15) comprising an inner wall (16) and an outer wall (17) and buffer water (21) in the gap between the inner wall (16) and the outer wall (17) of the buffer water tank (15), said buffer water tank (15) surrounding the one or more drain tanks (10), wherein a first piping structure (22) is defining a circuit for at least part of the buffer water (21) and comprising a heat exchanger (23) in thermal contact with a reservoir water tank (30), said reservoir water tank (30) being at a level above the buffer water tank (15), said reservoir water being in thermal contact with an environment and / or a second piping structure (24) is defining a circuit for at least part of the buffer water (21) and comprising a heat exchanger (25) in thermal contact with an environment, said heat exchanger (25) being at a level above the buffer water tank (15) and / or a seawater heat exchanger (26) in thermal contact with the buffer water (21) and seawater, said seawater heat exchanger (26) being located below seawater level outside the outer wall (17) of the buffer water tank (15).

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.

Targetry coupled separation refers to enhancing the production of a predetermined radiation product through the selection of a target (including selection of the target material and the material's physical structure) and separation chemistry in order to optimize the recovery of the predetermined radiation product. This disclosure describes systems and methods for creating (through irradiation) and removing one or more desired radioisotopes from a target and further describes systems and methods that allow the same target to undergo multiple irradiations and separation operations without damage to the target. In contrast with the prior art that requires complete dissolution or destruction of a target before recovery of any irradiation products, the repeated reuse of the same physical target allowed by targetry coupled separation represents a significant increase in efficiency and decrease in cost over the prior art.

The present invention relates to a reactor construction comprising an upper compartment above a reactor compartment, said reactor compartment being separated from the upper compartment by a radiation shield, wherein a molten salt reactor (MSR) is situated in the reactor compartment, the MSR comprising a reactor vessel with a reactor vessel lid assembly comprising a reactor vessel lid shield and a reactor vessel lid wherein a lifting element is situated in the reactor construction, the lifting element comprising: at least one bar being substantially vertical and axially adjustable along its longitudinal axis by a drive mechanism situated in the upper compartment, and wherein at least one through-hole for the at least one bar is provided in the radiation shield and wherein the reactor vessel lid shield has at least one receiving structure configured to engage with and lock to the at least one bar. The invention also relates to a method of performing a maintenance operation in the reactor compartment and a power barge comprising at least one reactor construction.

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 extraction system includes an absorbent framework configured to withstand the harsh environment of a molten salt reactor system and capture fission products found in the molten salt of such systems. The extraction system further includes means for removing the absorbent framework from the flow of molten salt, such that the absorbent framework may be processed to harvest the fission products. The absorbent framework may include a temperature resistant cartridge configured to house an absorbent composition. The present invention contemplates multiple absorbent compositions including metal-organic frameworks with unique structures to provide thermal stability, carbon nanotubes, and absorbent microspheres. The metal-organic frameworks may be synthesized by a variety of techniques to impart particular characteristics advantageous for use in a molten salt reactor system.

Advances in creating carbon-free emissions continue with nuclear power. This invention aims to achieve an environment with less radioactive pollution from pebble bed reactors. This invention uses stainless steel, niobium, or ferroniobium which does not form dust like carbon pebbles. The pebble bed reactor coolant will pass over the coated pebbles and not pick up radioactive dust as in old pebble models. This new design is more complicated and costs more than current designs. However, the cleanup of a used pebble bed reactor will be far less, and the health of the workers will be greatly improved through use of this invention. This practical design will enable pebble bed reactors to become approved at a faster rate than old designs.

A method and system for calibrating nuclear instrumentation of a reactor is disclosed. The system comprises a reactor configured to operate at a low power level and an external heater configured to heat the reactor to its operating temperature and maintain the reactor in a critical state. The reactor maintains its temperature at a steady state by repeating steps of reducing the heater's power and increasing the reactor's power by changing one or more reactivity settings, wherein the reduced heater's power is compensated by using the increased power generated by the reactor itself. The nuclear instrumentation is configured to measure the reactor's output power and compare it with the calculated reactor's power. Based on the discrepancy between the calculated power and the measured power exceeds a threshold; and the nuclear instrumentation is appropriately calibrated by adjusting one or more settings.

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).