27 results about "Dry storage" patented technology

Embodiments of a ventilated storage system and method are provided for enabling space-efficient storage of casks containing hazardous nuclear materials. Each of a plurality of dry storage casks has a ventilated overpack with air inlets at or near the bottom and air outlets at or near the top so that ambient air flows into the air inlets, through the overpack, and out of the air outlets for venting and cooling the hazardous nuclear material. A storage pad on which the casks sit each have a plurality of air flow channels that provide air to the air inlets situated at the bottoms of the casks. The storage pad enables the casks to be placed closer together in a more space-efficient triangular array.

The present disclosure belongs to the field of nuclear power technology, and particularly relates to a dry storage structure for spent fuel of a heavy water reactor. In the present disclosure, the storage module for storing spent fuel has a chamber inside, and a plurality of through holes are axially provided on the top plate of the chamber; each storage container is a cylindrical structure with an open top, each storage container is inserted into one of the through holes, and the bottom end of each storage container is fixedly connected to the bottom plate of the chamber; a plurality of fuel baskets are arranged in each storage container, and each fuel basket is used for placing spent fuel; each shielding plug is adapted to plug the opening at the top end of one storage container, thereby closing the storage container. By fixedly connecting the bottom end of each storage container to the bottom plate of the storage module, the supporting manner of the storage container is changed from being supported by the top plate of the storage module to being supported by the bottom plate of the storage module. It not only meets the requirement of dense storage of spent fuel but also meets the seismic requirement.

The application discloses a kind of digital fuel physics supervision method and system suitable for heavy water reactor, it is related to nuclear reactor fuel management technical field, system includes data acquisition module, document scale calculation interface, system management module and central processing module, central processing module configuration basic data, new fuel, FCO, spent fuel, dry storage area management unit.Method is standardized by data acquisition, whole-process digital control, dynamic monitoring and tracing three steps, realize fuel full life cycle closed-loop management.System adopts PDA to cooperate bar code / RFID to realize entity information acquisition and offline synchronization, constructs hierarchical correlation model, with new fuel isolation control, FCO closed-loop approval, spent fuel transfer verification, fine authority control and other functions, can improve management efficiency, reduce human error, strengthen data tracing and operation standardization, guarantee nuclear safety, provide support for management decision, suitable for heavy water reactor fuel physics supervision and whole-process management.

The application provides a kind of nuclear power plant dry storage spent fuel emergency evaluation method, system, equipment and medium, applied to dry nuclear horizontal modular storage system, the dry nuclear horizontal modular storage system includes concrete module and storage container, the method comprises: obtaining the information of natural disaster;According to the type and risk parameter of the natural disaster information of the natural disaster;In response to the risk parameter being higher than the response threshold, the radiation dose of the concrete module is obtained;According to the radiation dose, the effective multiplication coefficient of the storage container is obtained;In response to the effective multiplication coefficient being higher than the effective multiplication coefficient threshold, the storage container transfer operation is executed, can be integrated together by natural disaster risk assessment, radiation dose monitoring and effective multiplication coefficient control, form a complete emergency evaluation and response system, improve the overall efficiency of nuclear power plant in response to disaster.

The application relates to a preparation method of a layered B4C reinforced aluminum-based neutron absorption material plate, which comprises the following steps: using pre-oxidized aluminum powder and B4C powder to obtain a (B4C+Al2O3) / Al composite material plate through powder metallurgy, extrusion, rolling and other processes; placing mixed powder of B4C and 6061 Al between two (B4C+Al2O3) / Al composite material plates of the same size to obtain a layered blank sample of a (B4C+Al2O3) / Al plate with a B4C / 6061 Al mixed particle interlayer; riveting the layered blank sample, adopting a cumulative roll bonding method to roll the layered blank sample for multiple times to obtain a blank, and annealing the blank sample and cooling in air to obtain a layered B4C particle reinforced aluminum-based neutron absorption material plate. The preparation method of the layered B4C / Al-based neutron absorption material plate provided by the application has excellent mechanical properties and neutron absorption capacity, and can be used for dry storage and transportation of spent fuel.

The present invention relates to a dry storage module and a system comprising the same, the dry storage module having an improved mounting manner of a gas outlet and a cylinder body in a dry storage module for spent nuclear fuel of a vertical light water reactor, the dry storage module comprising: a housing forming a hexahedron-shaped accommodation space; a plurality of storage parts which are arranged in two rows in the accommodation space, are used for storing spent nuclear fuel, and extend for a long distance respectively; a hexahedron-shaped module part for accommodating the storage part; the storage tank is filled with spent nuclear fuel; a cartridge body surrounding the tank; a cartridge holder for attaching / detaching the cartridge body to / from the module part; the air inlet is formed in the side of the upper part of the shell; the air outlet is formed in the lower part of the shell; and shield grids provided at the respective inflow port and outflow port.

The present invention belongs to the technical field of dry storage of spent fuel from heavy water reactors, and specifically relates to a device and method for filling lead into a loading and unloading plug. The device comprises a loading and unloading plug, a lead filling funnel, a boiler, an inlet valve, a water trough, an electronic scale, a drain valve, and a heating tape. The loading and unloading plug is placed on the water trough, with a pouring hole formed on the top of the loading and unloading plug. The side of the loading and unloading plug is wrapped with a heating tape. The entire water trough is placed on the electronic scale. The top of the water trough is provided with an inlet valve connected to a pipeline, and the bottom of the water trough is connected to a drain valve via a pipeline. The lead filling funnel and boiler are located outside the water trough. The beneficial effect is that the top of the loading and unloading plug has four evenly distributed pouring holes along the circumference. The lead filling device, combined with the sequential pouring and water trough filling and draining methods, produces a "rock spray"-like liquid lead during the pouring process, maximally removing all gases from the lead solution, ensuring the final density and compactness, and effectively reducing deformation of the shielding plug caused by metal shrinkage in the loading and unloading plug. The lead filling quality fully meets technical requirements.

Methods for preparing and using at least one protective coating on industrial articles and storage systems are disclosed. In one example, the industrial components are dry storage cannisters for spent nuclear fuel or other waste materials. An example method for preparing at least one protective coating on dry storage cannisters for spent nuclear fuel and waste includes dissolving a dispersant in an organic solvent. The method further includes adding a polymer-derived ceramic (PDC) to the organic solvent and dissolved dispersant to create a pre-ceramic solution. The method further includes applying the pre-ceramic solution on a metal and / or alloy of industrial articles and storage systems such as the dry storage cannisters.

An integrated PWR nuclear reactor that requires no refueling and is cooled by natural convection. It is housed within a reactor containment unit which is transportable to a placement site and placed within an underground building that allows heat transfer from the reactor to the surrounding soil. Tire reactor containment unit encloses an integrated PWR nuclear reactor, a pressure and chemical control system, a safety system and a turbo generator. After its operational life, the reactor's water and air are replaced with inert gases, circulating by natural convection to remove decay heat to the surrounding soil. This enables the integrated PWR reactor, initially designed to generate electricity, to act as a dry storage facility for uranium fuel elements after the end of its operational life.

The application relates to a tool for separating a grab head from a fuel basket center column, which comprises a driving rod, a guide hub, a swing rod, a rotary table, an operating long rod and a pin, the middle part of the rotary table is provided with the guide hub, the end part of the rotary table is provided with the pin, one end of the swing rod is connected with the lower end of the guide hub, the other end of the swing rod is connected with one side of the pin, and the operating long rod is connected with the pin. The separating tool is simple in operation and high in practicability, can realize the separation of the grab head from the fuel basket center column, ensures the safe, efficient and orderly production of dry storage of spent fuel, and provides technical support and reference for subsequent similar power station related projects.

The invention relates to the technical field of welding, in particular to a welding head on spent fuel dry type storage container automatic welding equipment, which comprises a main mounting seat, an arc rack, a main mounting frame, a lower mounting frame, a welding torch and a wire feeding pipe, the arc rack is mounted on the main mounting seat through the main driving device, and the arc rack is driven by the main driving device to swing around the center line of the arc rack; the lower end of the arc rack is fixedly connected with a main installation frame, a lower installation frame is installed on the main installation frame through a vertical displacement adjusting device, a welding torch and a wire feeding pipe are installed on the lower installation frame, and the welding torch moves up and down in the vertical direction through the vertical displacement adjusting device. The device has four action functions of rotation, inclination angle, swing and AVC motion, the high-quality welding requirement of a spent fuel dry type storage container cover plate and a cylinder sealing weld joint is met, a main driving device guide wheel mechanism adopts a bolt roller bearing, friction is effectively reduced, motion smoothness of an arc rack is guaranteed, and the service life is prolonged.

This invention discloses a tiered drying and storage device for carbon black granulation and its usage method, relating to the field of carbon black granulation and storage technology. The invention designs a load-reducing, large-capacity tiered drying and storage device for carbon black granulation, mainly comprising a partition assembly, a feeding component, a flow meter, lifting rods and sealing devices, a partition rotation drive assembly, and an expansion joint. This invention allows an appropriate amount of carbon black granules to be injected into each storage chamber. A lifting rod with a tension spring is designed on the storage box, and multiple sealing devices are configured on the lifting rod. During discharge from the storage box, the lifting rod is pressed down in a tiered manner, causing the carbon black granules to be discharged layer by layer from low to high within the storage box. This enables a single storage box to continuously handle a large volume of storage and discharge, avoiding significant breakage of the carbon black granules during storage and transportation, and ensuring the efficiency of the carbon black granule storage and discharge process.

The present invention discloses a UHPC spent fuel dry storage vertical container structure and construction method, belonging to the technical field of spent fuel dry storage. The container comprises a bottom plate; a cylinder shell fixedly connected to the bottom plate; a concrete cylinder arranged around the cylinder shell; a top cover installed on the upper part of the concrete cylinder and the cylinder shell, and a base installed on the bottom plate; a plurality of reinforcing steel bars welded to the outer surface of the cylinder shell; an upper ring plate welded to the top of the cylinder shell; the concrete cylinder is formed by layered casting and curing, with the cylinder shell as the inner mold, the bottom plate as the bottom mold, the steel template as the outer mold, and the upper ring plate as the top mold. The steel template is removable, which facilitates the inspection of the construction quality and defects of the concrete cylinder, and enables non-destructive testing of the concrete cylinder during in-service operation and maintenance. Reinforcement steel bars are welded to the cylinder shell in advance, which facilitates construction and ensures welding quality. By leveraging the high strength and high bonding properties of UHPC concrete, the overall reinforcement amount is reduced, the cylinder wall thickness is reduced, and the site utilization rate is improved.

The invention discloses a UHPC spent fuel dry storage vertical container structure and a construction method, and belongs to the technical field of spent fuel dry storage. The cylinder shell is fixedly connected to the bottom plate; the concrete cylinder is arranged around the cylinder shell; the top cover is arranged at the upper parts of the concrete cylinder and the cylinder shell; the base is arranged on the bottom plate; a plurality of reinforcing steel bars are welded on the outer surface of the cylinder shell; an upper annular plate is welded to the top of the barrel shell. The concrete cylinder is formed by taking a cylinder shell as an inner mold, a bottom plate as a bottom mold, a steel template as an outer mold and an upper ring plate as a top mold through layered pouring and maintenance. The steel template can be detached, so that the construction quality and defects of the concrete cylinder can be conveniently detected, and the concrete cylinder can be subjected to nondestructive detection during in-service operation and maintenance; reinforcing steel bars are welded on the cylinder shell in advance, construction is convenient, the welding quality is guaranteed, by means of the high-strength performance and the high-binding-force characteristic of UHPC, the overall reinforcement amount is reduced, the cylinder wall thickness is reduced, and the site utilization rate is increased.

The present application relates to the technical field of spent fuel dry storage, and discloses a heavy water reactor spent fuel transport container drop disposal method. The method comprises the following operation steps: judging a drop scene of a spent fuel shielding transport container; if the drop occurs in a production plant, establishing a production plant site control area, and placing the spent fuel shielding transport container into a pool without cracks; if the drop occurs on a transport road, using hoisting equipment to hoist the spent fuel shielding transport container back to a transport vehicle, guiding the spent fuel shielding transport container back to the plant under the guidance of a security department guide vehicle, and placing the spent fuel shielding transport container into the pool without cracks; and if the drop occurs in a storage area, establishing a storage area site control area, and transporting the spent fuel shielding transport container back to the plant and placing the spent fuel shielding transport container into a storage pool without cracks. The method is convenient to use, easy to understand, and has high practicability, and can ensure the safety and reliability of spent fuel transfer and has high economic benefits.

The present application relates to the technical field of spent fuel storage, and discloses a spent fuel dry storage vault, which comprises a top air inlet vertical shaft for introducing natural ventilation, a bottom air chamber in communication with the air inlet vertical shaft, a storage chamber above the bottom air chamber, a plurality of shafts arranged in the storage chamber in a vertical direction, a heat generating body sleeved in the shafts in a spaced manner, an annular gap formed between the shafts and the heat generating body, the heat generating body containing spent fuel, the bottom air chamber in communication with a top air chamber through the annular gap, and an air outlet vertical shaft in communication with the top air chamber. Air for natural ventilation enters the air inlet vertical shaft through an air inlet, then enters the bottom air chamber, and then flows into the annular gap and the top air chamber, and is discharged from an air outlet through the air outlet vertical shaft, so that the flow path of the internal air is optimized, the storage chamber enhances the ventilation efficiency and heat exchange performance in a combined manner of heat conduction, convection and radiation heat exchange, the decay heat of the spent fuel in the heat generating body is discharged, and the safety and stability of the spent fuel dry storage vault are ensured.

The present disclosure relates to a spent nuclear fuel dry container having internal oxygen and moisture removal functions. The spent nuclear fuel dry container having internal oxygen and moisture removal functions comprises an oxygen and moisture removal apparatus including: an oxygen removal unit capable of removing oxygen contained in the internal space; and a moisture removal unit capable of removing moisture contained in the internal space.

The application discloses a thick-wall SA350Gr.LF3 large forging for a transfer container of a spent fuel dry storage system, which comprises a SA350Gr.LF3 large forging body, and the components contained in the large forging body and the mass percentage content (wt.%) thereof are as follows: C: 0.05%-0.15%; Cr: 0.10-0.20%; Mo: 0.04-0.06%; V: 0.01-0.03%; Nb: 0.01-0.02%; Al: 0.013-0.017%; N: 80-120ppm; Si: 0.20-0.30%; Mn: 0.70-0.80%; Ni: 3.5-3.7%; P≤0.006%; S≤0.003%; and the balance is Fe. The application further discloses a manufacturing process of the large forging, and the low-temperature toughness of the SA350Gr.LF3 large forging can be improved.

Disclosed are various embodiments of a simplified economic ventilated metal storage system (SEVMSS) for enabling hazardous radioactive spent nuclear fuel in a contaminated pool to be loaded and stored in a metal canister and then placed within a passively ventilated metal overpack on a dry storage pad, without use of a transfer cask. The embodiments use an insert ring and a basin cup at respectively the top and bottom of the overpack to seal the annulus space of the overpack while the overpack resides in the pool. After cooling of the overpack and removal from the pool, the insert ring is replaced with a vented lid and the basin cup is removed. The overpack with canister is then placed on the dry storage pad with a seismic stability ring attached to its bottom or is placed in a recessed opening of a ventilated storage pad.

The invention discloses a spent fuel gamma field irradiation system and method for a pebble-bed high-temperature gas cooled reactor, as gas is arranged around a spent fuel tank, gamma rays cannot be attenuated due to medium absorption, so that an irradiation device can receive gamma rays with higher intensity, and the irradiation efficiency is improved. The spent fuel tank is surrounded by the concrete wall, so that the safety protection for radiation is increased, and the risk of radiation leakage is reduced. By setting the interval between the spent fuel tank and the concrete wall, the size of the irradiation space can be accurately controlled, so that the irradiation effect is optimized. The gamma field irradiation device and method can be used in various research fields, such as radioactive waste treatment, material irradiation modification, nuclear technology application and the like. The dry storage mode reduces the requirement for a cooling system, so that the operation cost can be reduced, and meanwhile, the economic benefit is also improved by efficient irradiation utilization. The radiation pollution to the environment can be reduced by effectively controlling the irradiation space and utilizing the gamma rays.

The present invention relates to the technical field of storage devices, and particularly to a storage tank for chemical raw materials, which comprises a tank body. A support column is arranged on the outer wall of the bottom of the tank body. A fixed hopper is fixedly arranged inside the tank body through a fixed rod. A movable hopper is movably arranged in the fixed hopper. A communicating pipe is communicated with the top end of the movable hopper. A feeding pipe is fixedly arranged through the upper surface of the tank body, and the bottom end of the feeding pipe is located in the communicating pipe. A second discharging pipe is communicated with the bottom end of the fixed hopper, and the second discharging pipe penetrates through the bottom end of the tank body. Sealing covers are arranged at the ends of the first discharging pipe and the second discharging pipe. The present invention is convenient for adjusting the storage space in the tank according to the storage amounts of different chemical raw materials, is more flexible in use, and can effectively ensure that a dry storage environment can be maintained in the tank after feeding, and the use effect is better.

The invention discloses a preparation method of an aluminum-based boron carbide composite material. The aluminum-based boron carbide composite material is composed of boron carbide particles, an aluminum matrix, a nano reinforcement and a coherent interface formed by the nano reinforcement and the matrix. The boron carbide particles absorb neutrons, the nanometer reinforcement stabilizes an aluminum matrix structure, good room-temperature and high-temperature mechanical properties are provided, particularly, severe degradation of the strength of the aluminum-based boron carbide composite material in a high-temperature service environment (200-350 DEG C) is avoided, the service life of the material is prolonged, and the reliability of the material is improved. The aluminum-based boron carbide composite material is suitable for application scenes such as spent fuel dry storage and transportation treatment.

Disclosed are various embodiments of a simplified economical ventilated metal storage system (SEVMSS) that can load and store hazardous radioactive spent nuclear fuel in a contaminated pool in a metal can and then place it in a passively ventilated metal package on a dry storage mat without the need to use a transfer barrel. The embodiment uses an insertion ring and a basin cup at the top and bottom of the package, respectively, to seal the annular space of the package when the package is located in the pool. After the package cools and is removed from the pool, the insert ring is replaced with the vent cover and the basin cup is removed. The package with the can is then placed on a dry storage mat with a shock-resistant stabilizing ring attached to the bottom thereof, or in an embedded opening of a ventilated storage mat.

The invention relates to the technical field of welding, in particular to spent fuel dry type storage container double-machine-head automatic welding equipment which comprises a main supporting seat, the main supporting seat is arranged on a base, an upper rotating device and a lower rotating device are sequentially arranged on the main supporting seat from top to bottom, and a first radial displacement adjusting mechanism is arranged on the upper rotating device; the first radial displacement adjusting mechanism is connected with the upper welding head, the upper rotating device is used for adjusting the angle of the upper welding head, and the first radial displacement adjusting mechanism is used for adjusting the radial distance of the upper welding head; the second radial displacement adjusting mechanism is connected with the lower welding head, the lower rotating device is used for adjusting the angle of the lower welding head, and the second radial displacement adjusting mechanism is used for adjusting the radial distance of the lower welding head. The equipment is reasonable in design, and can be qualified for sealing welding seam welding of the spent fuel dry type storage container cover plate and the cylinder body; the equipment adopts a double-machine-head design, a single machine head and double machine heads can be independently controlled, and the welding construction efficiency is high.

The embodiment of the invention provides an arrangement method and device for spent fuel assemblies and a dry-process storage container, and the arrangement method comprises the following steps: carrying out radial partitioning on the dry-process storage container to obtain a plurality of storage areas, and pre-arranging each spent fuel assembly on the plurality of storage areas; arranging all the pre-arranged spent fuel assemblies for the first time according to a preset rule on the basis of the weight factors; and adjusting and arranging the corresponding spent fuel assemblies for the second time based on the burnup distribution of the fuel rods in different directions in the spent fuel assemblies. According to the embodiment of the invention, through two-time optimized arrangement, on the premise that the dry-method storage container meets the critical safety and thermotechnical safety limits, the burnup of each storage area of the spent fuel assembly in the dry-method storage process is more uniform; the problems that in the dry-method storage process of a dry-method storage container, burnup of a peripheral local area is excessively concentrated, and the radiation source item is too large are solved.

The invention relates to the technical field of spent fuel storage, and discloses a spent fuel storage well for a test and a design construction method.The spent fuel storage well for the test is characterized in that an air inlet channel is arranged in the vertical direction, and ventilation is conducted in the air inlet channel from top to bottom; one end of the lower air chamber is communicated with the lower end of the air inlet channel; the upper air chamber is positioned above the lower air chamber; the upper air chamber is communicated with an exhaust channel which is vertically arranged; the storage chamber is positioned between the upper air chamber and the lower air chamber; the upper air chamber is communicated with the upper end of the storage chamber; the multiple storage unit assemblies are arranged in the storage chamber at intervals and serve as containers for containing the simulated spent fuel. Simulated spent fuel is placed in the storage unit assembly through the spent fuel storage well for testing, and the difficulty of experimental research of a spent fuel dry storage ventilation technology is overcome; the ventilation cooling effect of the whole storage chamber under extreme climates such as windless climates and high-temperature climates can be researched, so that basic test research can be better carried out.

A dry storage systems for radioactive nuclear waste materials may include a double-walled canister system. The canister system may include a canister having a tubular inner shell defining an internal cavity for storing nuclear waste material, a first lid sealably welded to a first end of the inner shell, a primary base plate defining a peripheral edge portion and having an annular closure flange, and an annular full thickness butt weld formed at an abutment joint between the annular closure flange and a second end of the inner shell. The inner shell, first lid, and first end closure may collectively define a sealed primary pressure retention barrier. A tubular outer shell may adjoin the inner shell. The outer shell may be welded to the canister to form a hermetically sealed secondary pressure retention barrier.