19 results about "Pool-type reactor" 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 application is suitable for the field of nuclear reactor technology and discloses a filtering device and filtering method for a lead-bismuth cooled pool type reactor, which comprises a fixing assembly, a branch pipeline and a filtering assembly; the fixing assembly is arranged on the side of the main channel, and the fixing assembly comprises the branch pipeline in which the filtering assembly is detachably installed; the branch pipeline is connected with the side of the main channel through the fixing assembly to form the branch pipeline, and the filtering assembly is used for filtering and purifying in the branch pipeline without providing filtering power by itself; the filtering device as a whole can be arranged in the pool type reactor to ensure the integrity of the boundary of the reactor body; the filtering assembly has a simple structure and is convenient to install and replace, and can be operated in the reactor for a long time, so that the filtering device has a long service life and the replacement period of the filtering device is reduced.

The application discloses a kind of liquid metal cooling pool type reactor multifunctional passive residual heat removal systems based on heat pipe, belongs to reactor system component design technical field, the system is by high-temperature heat pipe, main container wall pit, gas storage tank, storage tank valve, gas heater, gas output pipe, gas input pipe, air extractor, safety container, main container, reactor pit, cold air descending passage, cylindrical thermal insulation layer, hot air ascending passage, connecting pipeline, exhaust chimney, heat radiation plate and in-pile fixed facility composition.The application can be in the condition of reactor total plant power failure, main heat exchanger water interruption and earthquake and other accident conditions, start passive accident residual heat removal system, and the residual heat of reactor core is removed to final heat sink by high-temperature heat pipe.Reactor is in low-power operation or shutdown condition, and auxiliary heating is carried out to in-pile liquid metal, to ensure that coolant is in molten state and promote flow.The system structure is simple, and has independence, passivity, inherent safety.

The present application discloses an online replacement device for in-core irradiation targets in a swimming pool-type reactor, which is used to solve the problem of existing reactors requiring shutdown for in-core target replacement. The online replacement device provided by the present application inserts or removes the target through the irradiation channel via a target hoisting connecting rod and a target driving mechanism. During the withdrawal of the old target, the compensating target floats up due to the buoyancy of the coolant and eventually remains in the irradiation channel due to the action of a petal-shaped stopper. During the insertion of the new target, the compensating target is pushed out of the irradiation channel by the new target. After the stopper retracts, the compensating target can be withdrawn from the core in the same manner as the old target and then replaced. During the entire target replacement process, the overall reactivity and moderation ratio of the core are not significantly disturbed, so there is no need to shut down and restart the core to replace the target. This shortens the target replacement time period, improves irradiation efficiency, reduces the complexity of the target replacement operation, and improves operational safety.

The present invention is applicable to the technical field of nuclear reactors, and discloses a filtering device and filtering method for a lead-bismuth cooled pool-type reactor. The filtering device comprises a fixed assembly, a branch pipe, and a filtering assembly; the fixed assembly is arranged on the side surface of a main channel, and the filtering assembly is detachably mounted in the branch pipe; and the branch pipe is connected to the side surface of the main channel by means of the fixed assembly, and the filtering assembly performs filtration and purification in the branch pipe, without requiring the filtering assembly itself to provide filtering power. The filtering device as a whole can be arranged in the pool-type reactor, ensuring the integrity of the reactor body boundary; and the filtering assembly has a simple structure, is convenient to mount and replace, can operate for a long time in the reactor, ensures a long service life of the filtering device, and reduces the replacement cycle of the filtering device.

Systems limit backflow through a nuclear reactor cores from a hot pool to a cold pool. Example systems include coolant risers and / or one-way flow structures before a coolant inlet for the reactor. The coolant riser provides coolant that will flow under gravity alone into the reactor despite hot pool pressure head. Fluidic diodes and / or check-valves prevent nearly all reverse flow. Such structures may be positioned with the flow limiter before the riser in the normal direction of coolant flow into the inlet. Such structures may be positioned anywhere they can functionally provide coast down cooling and prevent reverse flow, including as a pump annulus or pool. For a sodium-cooled fast reactor, the riser and fluidic diode may provide sufficient volume to cool the reactor with forward coolant flow for an entire reactor coast down period, when the reactor is shut down and generating only decay heat.

The invention discloses an experimental measurement system and an experimental measurement method for fission product aerosol behaviors under a pool type lead-bismuth reactor accident, and belongs to the field of lead-based fast reactor thermal hydraulic safety. A reaction container and a telescopic rod are arranged in the pressure container; the reaction container is arranged at the bottom end of the pressure container, the telescopic rod is arranged at the top end of the reaction container, the telescopic rod is connected with the thermocouple, and the thermocouple is inserted into an insertion opening in the top end of the pressure container and is controlled to ascend and descend through the telescopic rod. The operation environment of a pool type reactor is simulated, then sampling analysis of the fission products in the lead-bismuth coolant in the whole process is achieved, the chemical combination decomposition characteristics and physical characteristics of the fission products can be known more visually, and due to the design of the pressure stabilizing system, the gas conveying system and the ventilation system, research parameters are more comprehensive, and the research efficiency is improved. Therefore, the evaporation rule of the fission product aerosol under the accident condition can be fully mastered conveniently according to most parameters of the pool type lead bismuth reactor under the accident condition.

The invention discloses a pool type reactor capable of automatically changing materials, and relates to the technical field of nuclear reactors. The plurality of fuel assemblies are arranged and distributed in the reactor shell; the cock mechanism is arranged at the top of the reactor shell and is rotationally connected with the reactor shell, so that a closed cavity is formed in the reactor shell, a plurality of hole channels are formed in the cock mechanism, and a hole channel plug is mounted on each hole channel; the grabbing mechanism is arranged above the cock mechanism; and the moving mechanism is arranged above the grabbing mechanism, and the moving mechanism is fixedly connected with the grabbing mechanism. The pool type reactor overcomes the technical problems of inconvenience in fuel reloading, short service life of in-reactor reloading and high failure rate of a liquid metal cooling reactor in the prior art, and the pool type reactor which can realize out-of-reactor reloading and is convenient and automatic in reloading is provided.

The invention discloses a low-flow-resistance frame type control rod assembly and belongs to the technical field of nuclear. The control rod assembly mainly comprises an upper connecting base, a lower connecting base and a supporting pipe, the supporting pipe is fixedly connected with the upper connecting base and the lower connecting base through connecting rib plates arranged at the two ends respectively, and axial gaps are formed between the upper end face of a pipe body and the lower end face of the upper connecting base and between the lower end face of the pipe body and the upper end face of the lower connecting base. The axial gap provides a flow passage for the coolant. The low-flow-resistance frame type control rod assembly can effectively reduce the flow resistance of a coolant during axial flow, improve the balance of flow distribution of a pool type reactor core and improve the safety of the reactor.

The application provides a pool type reactor pit structure, relates to the technical field of nuclear reactors, and comprises a pit, an upper component, an air inlet channel, at least two air outlet channels, and a self-shielding body. The pit is recessed inward from the top surface of the self-shielding body to accommodate a pressure vessel. The upper component is fixed to the top surface of the self-shielding body and closes the pit opening. The fluid space is defined among the upper component, the cavity wall of the pit and the pressure vessel. The air inlet channel extends outward from the upper part of the self-shielding body to the lower cavity wall of the pit. The air outlet channel extends outward from the top surface of the self-shielding body to the upper cavity wall of the pit. All the air outlet channels are uniformly arranged on one side of the central axis of the pit, and the air inlet channel is arranged on the other side of the central axis of the pit. The application avoids direct penetration of the self-shielding body, can stop the leakage of radioactive substances in the reactor, realizes 360-degree envelope ventilation of the reactor pressure vessel, can continuously cool the reactor pressure vessel, and has better heat dissipation effect.

Systems limit backflow through a nuclear reactor cores from a hot pool to a cold pool. Example systems include coolant risers and / or one-way flow structures before a coolant inlet for the reactor. The coolant riser provides coolant that will flow under gravity alone into the reactor despite hot pool pressure head. Fluidic diodes and / or check-valves prevent nearly all reverse flow. Such structures may be positioned with the flow limiter before the riser in the normal direction of coolant flow into the inlet. Such structures may be positioned anywhere they can functionally provide coast down cooling and prevent reverse flow, including as a pump annulus or pool. For a sodium-cooled fast reactor, the riser and fluidic diode may provide sufficient volume to cool the reactor with forward coolant flow for an entire reactor coast down period, when the reactor is shut down and generating only decay heat.

The invention belongs to the technical field of pool type reactors, and particularly relates to a pool type reactor cross-dimension coupling analysis method under cooling of a reactor vessel cooling system. The method comprises the following steps: S1, analyzing the demand of pool type reactor thermotechnical safety characteristics under the cooling condition of a reactor vessel cooling system, and splitting a pool type reactor computational domain according to an analysis result; s2, constructing a corresponding physical calculation model according to the pool type reactor calculation domain; s3, constructing a physical model capable of analyzing the operation characteristics of the reactor after the reactor vessel cooling system is put into use; s4, determining a data transfer relationship among the programs, and developing a coupling scheduling interface and a data transfer interface of each physical solution program; and S5, performing model simplification and conservative assumption on the calculation area, and constructing the calculation area. The method supports accurate analysis of cooling lower pool type in-reactor flow heat transfer characteristics of a reactor container system and heat carrying capacity of a waste heat export system, and has the advantages and characteristics of high accuracy, strong functionality and wide application range.

The application discloses a liquid metal pool type reactor temperature field-flow field-oxygen distribution field multi-field coupling calculation method, which comprises the following steps: a three-dimensional geometric model is established and a grid is divided for a flow calculation domain of the liquid metal pool type reactor; a fluid flow field and a temperature field are solved; an oxygen distribution field is calculated based on a component transport equation, a gas-liquid interface is captured by using a fluid volume method, and an interface mass transfer source term is established according to a concentration gradient; oxidation and reduction reactions are embedded into the transport equation source term through a user-defined function, and the oxygen consumption and generation rate of the wall surface are dynamically updated; a step-by-step iteration algorithm is adopted to realize the coupling solution of the temperature field, the flow field and the oxygen distribution field. The method can output the flow velocity, temperature and oxygen concentration distribution in the liquid metal coolant system, analyze the oxygen migration law and the corrosion sensitive area, and provide a theoretical basis and engineering guidance for the oxygen concentration control, corrosion protection and safety design of the liquid metal pool type reactor.

The invention provides a water return pipeline, a pool type reactor and an operation method thereof. The water return pipeline comprises a body, one end of the body is used for extending into a pool, the other end of the body extends out of the pool and is connected with one end of a discharge pipeline, and the other end of the discharge pipeline extends to a reactor core in the pool; the section, extending into the pool, of the body is provided with a reducing section which is connected with an exhaust pipeline, one end of the exhaust pipeline is connected with the reducing section, the other end of the exhaust pipeline extends upwards to the first position of the body, and the first position is higher than the reducing section. The water return pipeline comprises a first flow path and a second flow path, and the first flow path is configured in the mode that when siphoning occurs, water flow enters the body from one end of the body and flows to the other end of the body in the extending direction of the body, and liquid phase flow is provided; and the second flow path is configured as follows: when siphoning occurs, gas is separated out when water flow passes through the reducing section, and the gas enters the exhaust pipeline and upwards flows to the other end of the exhaust pipeline in the extension direction of the exhaust pipeline, so that two-phase flow for breaking siphoning is formed in the first flow path.

The application belongs to the technical field of loading and unloading of pool type reactor irradiation devices, and particularly relates to a use method of a double-layer pipe type hoisting device for loading and unloading of irradiation devices, which comprises an inner layer pipe and an outer layer pipe, the inner layer pipe is arranged inside the outer layer pipe, the upper end of the inner layer pipe is clamped with the upper end of the outer layer pipe, the lower end of the inner layer pipe is clamped with the lower end of the outer layer pipe, the lower end of the inner layer pipe is connected with a grabbing head, and the hoisting head is used for detachable connection with the irradiation device. The double-layer pipe design can make the inner and outer layer pipes work cooperatively, effectively improve the rigidity and stability of the device, reduce the deformation and errors generated in the hoisting process, the torsion plate additionally arranged can not only transmit greater torque, but also provide axial limiting function for the inner layer pipe and the grabbing head, prevent the grabbing head from accidentally falling, and enhance the safety of the device.

The present invention discloses a waterproof and heat-insulating sleeve and a pool-type reactor having the same. The pool-type reactor includes: a water pool; a pressure vessel and a reactor core, the reactor core is arranged inside the pressure vessel, and the pressure vessel has a vessel inlet and a vessel outlet; a sleeve, the sleeve is fixedly installed in the water pool and immersed below the liquid level of the water pool, the pressure vessel is installed inside the sleeve to be isolated from the water pool, and the sleeve is provided with a through hole for a primary loop pipeline to penetrate. In the pool-type reactor of the present invention, a sleeve is arranged outside the pressure vessel and the reactor core. The sleeve can provide a waterproof space for the control rod drive mechanism, avoid the inconvenience of underwater design or operation, play a heat-insulating role for the pressure vessel and the reactor core, reduce the heat exchange of the pressure vessel wall, reduce heat loss, and the sleeve can play a role in radioactive shielding for the reactor core, reduce the radiation dose, and has good safety and practicability.

The invention provides an analysis method for flow distribution of a pool type reactor core. The analysis method comprises the following steps: calculating flows of a plurality of equivalent channels according to a parallel channel principle and a classical hydraulics relational expression so as to determine the flow of a standard fuel assembly channel, the flow of a following fuel assembly channel and the bypass flow of a bypass channel; determining reactor core inlet flow distribution factors of each standard fuel assembly and each following fuel assembly according to the three-dimensional CFD model of the reactor core and a computational fluid mechanics method; determining real reactor core inlet mass flow of each standard fuel assembly and each following fuel assembly based on the reactor core inlet flow distribution factor, the flow of the standard fuel assembly type channels and the flow of the following fuel assembly type channels; and determining the flow distribution of the reactor core according to the real reactor core inlet mass flow and bypass flow of each standard fuel assembly and each following fuel assembly.

A pool reactor safety management system comprises a shutdown device, a passive residual heat removal device, a main circulation device, an auxiliary circulation device and a passive circulation device, wherein the shutdown device is used to realize shutdown under accident conditions; the passive residual heat removal device forms natural circulation between a reactor pool and an external heat sink; the main circulation device provides a circulation pipeline and drives the circulation of cooling water under normal conditions; the auxiliary circulation device comprises an auxiliary circulation pump connected in parallel with the main circulation pump; and the passive circulation device comprises a natural circulation valve arranged in a lower chamber of the reactor. The system can effectively avoid overheating of the cooling water under accident conditions, quickly switch the flow direction of the cooling water from forced convection under normal conditions to natural convection under accident conditions, prevent flow stagnation, and effectively improve the safety and reliability of the pool reactor. The application also provides a pool reactor safety management method.

This application provides an immersion thermoelectric conversion device, including a fixed frame, a medium piping system, a power management module, and multiple energy conversion modules. All energy conversion modules are fixed inside the fixed frame. The medium piping system is located at the top of the fixed frame. Each energy conversion module mainly consists of an energy conversion unit and a heat exchange unit. The heat exchange units in the multiple energy conversion modules are connected through the medium piping system. The heat exchange units are used to exchange heat with the external medium connected to the medium piping system. The energy conversion units are used to generate electrical energy under the influence of the temperature difference between the heat exchange units. The power management module has functions of power collection, circuit series-parallel switching, and DC-DC transformation, used to convert the DC power output from the energy conversion units in the multiple energy conversion modules into DC power with a stable voltage. This application addresses the technical problem of the lack of adaptability of existing static thermoelectric conversion devices to scenarios such as pool reactors and underwater fixed power sources by adopting a frame-type fixed multi-module design.