797results about "Portable shielded containers" patented technology

The embodiment of the invention relates to the field of radioactive waste treatment, in particular to a sealing device and curing equipment. According to the sealing device and the curing equipment provided by the embodiment of the invention, the blocking assembly and the sealing assembly jointly block the first opening formed by the material treatment device, so that the material treatment device is subjected to double sealing, and the internal material treatment environment is more stable; the locking assembly is driven to move in the circumferential direction so as to fix the plugging assembly to the sealing assembly, meanwhile, the locking assembly is arranged to be axially static so as to further reinforce fixation between the plugging assembly and the sealing assembly, and the material containing device can be more stable in the material treatment device; and good sealing performance and stability in the material treatment process are ensured.

The embodiment of the invention relates to the field of radioactive waste treatment, in particular to a material containing device and curing equipment. The first containing piece and the second containing piece of the material containing device are arranged to be in a detachable and separable form, so that powdery radioactive materials cannot escape from a seam, and meanwhile, after the powdery materials are pressed into solid materials, the first containing piece and the second containing piece can be separated; the solid materials contained in the first containing part can be independently transferred, the material containing device is prevented from being integrally transferred when the solid materials are transferred, and the transferring efficiency of the solid materials is improved. According to the curing equipment, the material containing device is adopted as a material conveying carrier, materials in different stages and states in the curing process can be contained, and leakage of the materials is prevented; meanwhile, in the whole curing process, form transformation of the materials can be achieved without replacing the containing device, the operation process is simplified, material spill caused by replacing the containing device is avoided, and therefore the curing efficiency is improved.

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 utility model relates to a nuclear power high-radiation object containing device and containing and transferring equipment. The containing and transferring equipment comprises the nuclear power high-radiation object containing device. The nuclear power high-radioactivity storage device is specially designed for underwater operation, and can safely store and seal high-radioactivity waste under the condition that normal operation of a reactor is not affected. The sealing mechanism ensures that the radioactive substance storage space is completely sealed in the transferring and long-time storage process, radioactive substances are prevented from leaking, and the safety of the treatment process is greatly improved. And secondly, the torque input end allows torque to be input through an external tool to achieve rotation of the lock cylinder, so that the closing or opening action is rapidly and effectively completed, the operation process of containing and closing the radioactive substances is simplified, and the containing and closing efficiency of the radioactive wastes is improved.

The invention relates to a reactor core high-level detector pulling mechanism which provides effective radiation protection in the pulling process of a detector by introducing a shielding cylinder, so that the radiation dosage possibly received by an operator during operation is remarkably reduced, and the safety of a working environment is improved. Secondly, an alignment connecting device with an alignment camera is further arranged, the position of the lifting and moving assembly can be monitored and adjusted in real time, it is ensured that the lifting and moving assembly is accurately aligned and connected with the detector to be pulled out, and in the process that the shielding cylinder gradually goes deep into the reactor core water pool, the detection accuracy is improved. And position interference between the shielding cylinder and other structural members in the reactor core can be avoided, so that the problem that accurate butt joint is difficult in a traditional method is solved, and the detector pulling-out efficiency and the operation safety are improved.

The invention relates to a nuclear reactor detector assembly recovery system and method, and the system comprises a shielding transfer device which is used for pulling out a detector from a nuclear reactor and transferring the detector to a preset position; the coiling equipment is arranged on the guide rail assembly and driven by the lifting assembly to move below the liquid level of the component pool, and the coiling equipment is used for coiling part of the detector; and the dismantling platform is arranged at the pool opening of the component pool and used for bearing the hanging frame assembly, the shearing assembly and the clamping assembly. The working process of the shielding transfer equipment and the working process of the coiling equipment can be independently carried out, so that the shielding transfer equipment can work continuously, and the recovery working efficiency and the recovery convenience of the detector are improved; the corresponding detector is pulled out, released and coiled under the liquid level, shielding is carried out through the shielding transfer equipment in the transfer process, the problem that the radioactivity of the lower section of the detector is high is effectively solved, and the safety of the site construction environment is improved.

The invention provides an offshore nuclear power platform containment equipment transfer system and method.The offshore nuclear power platform containment equipment transfer system comprises a shielding silo, a platform temporary workshop, a shore-based crane and a shore-based maintenance workshop, the shielding silo is arranged at a shielding door at the top of a containment and used for hoisting and shielding equipment to be maintained, and the platform temporary workshop is arranged on a platform deck and used for hoisting and shielding the equipment to be maintained; according to the invention, receiving, hoisting and transferring facilities are provided, it is ensured that the equipment to be maintained is effectively contained in the containment and the shielding silo, multi-line parallel operation can be realized, and the equipment maintenance out-of-cabin process has higher efficiency, safety and reliability.

The nuclear power station pool foreign matter collecting and transferring device comprises a shielding container and a collecting basket, the shielding container comprises a first containing cavity and is provided with shielding materials capable of shielding rays, and the collecting basket comprises a second containing cavity and can be arranged in the first containing cavity; and drainage structures are arranged on the collecting basket and the shielding container. According to the nuclear power station pool foreign matter collecting and transferring device, after the foreign matter is collected, the foreign matter does not need to be transferred underwater again, the collecting basket can be placed in the shielding container or the foreign matter is directly placed in the shielding container, and the shielding container can shield the foreign matter with high radiation dose; radiation of foreign matters to human bodies and the environment can be reduced, the operation risk of personnel is reduced, and use is simpler and more convenient; the shielding container and the collecting basket can be used in cooperation and can also be used independently, and on-site flexible use is facilitated; the arrangement of the drainage structure facilitates the discharge of radioactive residual water in the foreign matters, so as to reduce the foreign matter collection and transfer weight.

An improved system for receiving and storing a radioactive salt solution includes a tank configured to receive the radioactive salt solution while preventing criticality accidents, a solution inlet for carrying the radioactive salt solution to the tank, an overflow bottle, and a cap sealing the top end of the tank. The cap includes a lateral wye fitting having a lateral pipe configured to direct the radioactive salt solution from the solution inlet into the tank, a vertical pipe configured to direct gases from the tank to a ventilation system, and an overflow line configured to carry excess radioactive salt solution from the tank to the overflow tank. An air gap between the lateral pipe and the solution inlet prevents backflow of the radioactive salt solution into the solution inlet. A control system includes a level switch configured to provide a signal that the tank contains a maximum volume of the radioactive salt solution, a first valve configured to terminate flow of the radioactive salt solution to the lateral pipe upon receipt of the signal from the level switch; and a second valve configured to allow flow of the radioactive salt solution from the tank to the overflow line.

Provided herein shielded radioactive storage devices including a hollow body defining an interior cavity, a first well positioned within the interior cavity, including a first well casing, and defining a first well cavity having a first well opening, the first well cavity and first well opening sized to receive a radioactive payload, a second well positioned within the interior cavity, including a second well casing, and defining a second well cavity having a second well opening, the second well cavity and second well opening sized to receive a second radioactive payload, a shield casing extending around and spaced apart from the first and second well casings to form a shielding cavity between the shield casing and the first and second well casings, and radiation shielding material filling the shielding cavity to surround the first and second well casings.

The invention relates to a shielding transportation device for an Sr-90 radioactive source, which comprises a shielding container, a protective cover and a transportation bracket, the protective cover is arranged at the upper part of the shielding container, and the transportation bracket is arranged at the lower part of the shielding container; the shielding container comprises a shielding container cylinder, the shielding container cylinder comprises an outer container and an inner container, the inner container is arranged in the outer container, a spring is arranged below the inner container, and the inner container is used for loading an Sr-90 radioactive source. Compared with the prior art, the device can meet the requirement that the radioactive source is loaded and unloaded in a horizontal state, can prevent the radioactive source from scattering under the condition of a transportation accident, still has enough shielding capability, has good transportation interface performance, and can ensure the safety in the transportation process. The chemical forms of the transported Sr-90 comprise 90SrO, 90Sr (NO3) 2 and 90SrTiO3, and the item forms of the transported Sr-90 cover powder, ceramics, solutions, pellets and the like.

The invention provides a radiation shielding assembly, a drug vial assembly system, a method of dispensing a drug vial assembly system, and a radiopharmaceutical infusion device. The radiation shielding assembly is used for shielding a medicine bottle assembly containing radiopharmaceuticals, and the medicine bottle assembly is provided with a puncture communication piece capable of transversely moving. The shielding body is provided with a top opening, a small bottle containing cavity and a combination port, and the medicine bottle assembly is contained in the containing cavity through the top opening. The containing cavity is provided with a circumferential matching wall, the distance between the matching wall and the vertical center line is gradually decreased from the starting end to the tail end, and a moving path is provided for assembly. The medicine bottle is guided to move along the wall, and the bottom puncture communicating piece is guided to transversely move inwards and is in butt joint with the combination port when reaching the assembly completion position. After assembly is completed, the puncture communicating piece is in butt joint with the combination port. According to the invention, only one needle puncturing the top of the medicine bottle is used as an inflow channel. Needle adjustment is not needed when medicine is nearly empty, operation is simplified, and the error rate is reduced.

The invention relates to a shielding body structure of a standing type radioactive internal pollution measuring system and a design method, and the shielding body structure comprises a personnel shielding cabin which comprises three vertical cylindrical surfaces, a first upper top plate arranged above the vertical cylindrical surfaces, and a first lower bottom plate arranged below the vertical cylindrical surfaces, the opening angle after connection is greater than 90 degrees; the detector shielding cabin comprises three vertical cylindrical surfaces, a second upper top plate and a second lower bottom plate, the three vertical cylindrical surfaces are continuously connected, the opening angle after connection is 90 degrees, and the opening direction formed by the three vertical cylindrical surfaces faces the opening direction formed by the three vertical cylindrical surfaces; and the detector supporting module is mounted in the detector shielding cabin and is used for supporting and fixing the detector. According to the invention, the problems of compact space, poor passing ability and high detection limit value of the detector after the detected person enters the shielding body structure in the prior art are effectively solved.

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.

The utility model relates to the technical field of nuclear fuel transportation, in particular to a mechanism convenient to mount and dismount and a nuclear fuel transverse transportation fixing device. Comprising a storage unit which comprises a storage grillwork, a storage head bin and a connecting cylinder; the disassembly locking unit comprises a clamping assembly, a pushing assembly, a gear, a fixing shaft and a pawl. The containing unit comprises a supporting bottom plate and a containing plate. The nuclear fuel container loading and unloading device has the beneficial effects that an operator can more easily complete the loading and unloading process, so that the nuclear fuel container can be quickly positioned and locked or unlocked, the loading and unloading time is shortened, and the dependence on professional tools is reduced; through the design of the pressing unit, the pressing unit can transversely press and fix the nuclear fuel assembly in the transportation container, so that in the transportation process of the nuclear fuel assembly, the stability of the transportation container can be improved, and the safety of the nuclear fuel assembly in the transportation process is ensured.

Disclosed example radiographic source exposure devices include: a radiographic source capsule having a radionuclide; a radiographic shield; a channel within the radiographic shield, the channel having a first end and a second end; and a replaceable tube configured to guide a radiographic source capsule between a stored position and an exposed position in which at least a portion of the radiographic source capsule is exposed to an exterior of the radiographic shield.

The utility model relates to a high-efficiency air supply and exhaust device of an artificial nuclear medicine split charging hot chamber cabinet. The air supply and exhaust efficiency is improved. Comprising an air supply and exhaust top chamber and a shielding sub-packaging middle heat chamber shielding in-out lower heat chamber which is respectively provided with a sealing protection front door, a static pressure air supply box and an exhaust fan box which are arranged in the air supply and exhaust top chamber in parallel are respectively downwards communicated with an air supply port close to the sealing protection front door at the upper part in the shielding sub-packaging middle heat chamber shielding in-out lower heat chamber through a non-return air supply pipeline; and an exhaust outlet which is far away from the sealing protection front door and is provided with an activated carbon filter at the lower part in the shielding split charging middle hot chamber and the shielding in-out lower hot chamber is downwards communicated through a non-return exhaust pipeline. The device has the advantages that the quality of exhausted air is guaranteed, air in the hot chamber is prevented from overflowing when the door is opened, and nuclide pollution of the air in the hot chamber can be kept at a reasonable low level through adsorption of internal circulating airflow.

The utility model is applicable to the field of nuclear waste treatment, and discloses a shielding device for high-radioactivity waste storage and transfer of a nuclear power plant, which comprises an outer barrel, a barrel cover, a hinge locking component and an inner barrel, the inner barrel is arranged in the outer barrel, the outer barrel is provided with an outer wall and an inner wall, the inner wall is fit with the inner barrel in shape, a radiation-proof material is filled between the inner wall and the outer wall, the outer wall is provided with a first lifting lug extending outwards, the barrel cover is arranged on the upper portion of the outer barrel, and a second lifting lug is arranged on the barrel cover. After radioactive waste is loaded into the inner barrel and the inner barrel is sealed, the inner barrel is then loaded into the outer barrel, the barrel cover and the outer barrel are locked through the hinge locking assembly, then an operator carries the outer barrel through connection of the first lifting lug and mechanical equipment, and when the barrel cover is opened and closed, the second lifting lug or a lifting appliance on the barrel cover can be selected according to an existing clamp and tool. The whole shielding device is simple in structure, the inner barrel, the outer barrel and the barrel cover are convenient and simple to install and carry, and the radiation time of operators is shortened.

The invention relates to a high radioactive substance shielding transfer mechanism which is provided with a shielding device which comprises a shielding cylinder and a lifting channel, so that a worker can be far away from a radioactive source in the process of replacing a detector assembly, the risk of radiation exposure is effectively reduced, and the health and safety of the operator are guaranteed. And secondly, a detector connecting device is further arranged, and the detector connecting device comprises a connecting hanging ring, a connecting cylinder and a locking piece, so that the end part of the detector can be quickly and stably locked or released, the operation process of dismounting the detector is simplified, and the working efficiency is improved. And the pulling device and the lifting device are combined for use, so that automatic extraction and installation of the detector are realized. The pulling assembly can slide in the lifting channel, is detachably connected with the detector connecting device through the pulling connecting assembly, and is matched with the driving of the lifting device, so that the stable pulling of the detector is ensured, and the dismounting of the detector is greatly facilitated.

A hazardous waste repository includes a directional drillhole formed from a terranean surface into a subterranean formation. The directional drillhole includes an access drillhole portion that includes an entry at the terranean surface sized to receive one or more hazardous waste canisters configured to enclose hazardous waste, a curved drillhole portion, and a substantially horizontal or inclined drillhole portion. The substantially horizontal or inclined drillhole portion includes a storage region sized and configured to store the one or more hazardous waste canisters. The repository includes a flow conduit formed or installed from the terranean surface into the subterranean formation and in fluid communication with the storage region. The flow conduit and the directional drillhole are configured to receive a flow of a liquid that circulates from the terranean surface, through the flow conduit and the storage region, and back to the terranean surface for a corrosion analysis of the liquid.

A container for a solid target material and a radioisotope produced by proton beam irradiation of the solid target material, the container having: a well, which is suited to support on its own bottom wall a portion of solid target material; a support body, which extends along a longitudinal axis and has a seat for housing the well in such a way that the bottom wall is arranged transversely to the longitudinal axis; and a lid, which comprises a central portion having a degrader foil for degrading the proton beam and can be fitted on the support body so that the central portion is arranged in the well to retain the portion of solid target material on the bottom wall and that the degrader foil is arranged above the portion of solid target material.

The present application relates to a kind of core high probe extraction mechanism, which provides effective radiation protection during the removal of the probe by introducing a shielding cylinder, significantly reduces the radiation dose that can be received by the operator when working, improves the safety of the working environment.Secondly, the present application also configures a positioning connection device with a positioning camera, which can monitor and adjust the position of the lifting moving assembly in real time, ensure its accurate alignment with the probe to be removed, and avoid positional interference between the shielding cylinder and other structural members in the core during the gradual deepening of the shielding cylinder into the core pool, thereby solving the problem of difficult accurate docking in traditional methods, improving the probe removal efficiency and operation safety.

The present invention relates to the technical field of the construction of a radiation field of a radiation source, and provides a safety protection device for a lifting rope of a radiation source, which comprises a two-section lifting rope of an underwater lifting rope and an above-water lifting rope, and the two sections of lifting ropes respectively adopt the redundancy mode of a main rope and a deputy rope. When the radiation source is in a non-operating state, the main body is submerged in a pool, and the lifting rope section connected to the radiation source is the underwater lifting rope, and the lifting rope section located above the pool and connected to the driving mechanism is the above-water lifting rope, and the two sections of lifting ropes are connected through a connecting limit ring. The safety protection device for the lifting rope of the radiation source of the present invention has a simple structure and is convenient to use. The underwater and above-water two independent lifting ropes can be independently protected and maintained. Each section of the lifting rope is provided with a main / deputy rope, and the double redundancy protection can avoid the overall fracture of the lifting rope; the rope can be safely replaced without contacting the radiation source.

A radiation barrier system comprising: a chemically reactive base layer; a first layer at least partially disposed above the base layer; the first layer comprising a first soil; a second layer at least partially disposed above the first layer; and the second layer comprising a second soil. The chemically active base layer is a hydro-geochemical filter barrier. The chemically active base layer mitigates soluble uranium or uranyl ion transport. The chemically active base layer filters out uranyl ions. The uranyl ions are filtered out by a process of surface adsorption to a phase added to a lithified soil composition.

The invention discloses a PET-CT (positron emission tomography-computed tomography) radiopharmaceutical closed automatic dispensing and dosing machine which comprises a machine base and an injection bin fixedly mounted on the machine base, an air cylinder mechanism is fixedly mounted at the top of the back of the injection bin, and a closed box is fixedly mounted on one side of the injection bin. And a transmission mechanism pushed by the air cylinder mechanism is installed in the closed box in a sliding mode, a mechanical clamping mechanism is installed at the bottom of the transmission mechanism in a transmission mode, and an arm support is fixedly installed at the position, located at the placing opening, in the injection bin. According to the invention, the mechanical clamping mechanism repeatedly acts to clamp the disposable syringe, the problem of more pipeline consumables is solved by directly adopting the mechanical clamping mechanism to extract liquid medicine at a fixed point and inject the liquid medicine at a fixed point, meanwhile, the flowing time of the stock solution in the pipeline is also reduced, the disposable syringe directly injects the stock solution into the heparin cap, and the operation is simple and convenient. And the accuracy of the nuclide value is ensured to the greatest extent.

Additive manufacturing compositions include low-absorbing particles or non-absorbing particles that have an absorbance for wavelengths of 300 nm to 700 nm that is equal to or greater than 0 Au and is less 1.0 Au, such as 0.001 Au ≤ absorbance ≤ 0.7 Au. Slurries including such particles and an uranium-containing particle and that are used in additive manufacturing processes have an increased penetration depth for curative radiation. Removal of low-absorbing particles or non-absorbing particles during post-processing of as-manufactured products results in pores that create porosity in the as-manufactured product that provide a volume accommodating fission gases and / or can enhance wicking of certain heat pipe coolant liquids. Low-absorbing particles or non-absorbing particles can be functionalized for improved properties, for example, with fissionable material for improved ceramic yields, with burnable poisons or stabilizers for increased homogeneity, with stabilizers for localized delivery of the stabilizer, or with combinations thereof.

The utility model relates to a shielding device and recovery system for a nuclear reactor detector assembly, and the shielding device comprises a shielding pipe body which is provided with a pipe cavity, and the pipe cavity is used for accommodating a high-level radioactive detector; the driving assembly is arranged outside the shielding pipe body; the pulling assembly is arranged in the tube cavity, one end of the pulling assembly is connected with the driving assembly through a traction strip, and the other end of the pulling assembly is used for being connected with a high-level radiometric detector; the pulling assembly is driven by the driving assembly to move in the axial direction of the shielding tube body so that the high-level detector can be contained in the tube cavity or the high-level detector can be discharged out of the tube cavity. The structure design is ingenious, safe transfer of the high-level radioactive detector is achieved, radiation can be effectively shielded through the shielding pipe body, and operators and the surrounding environment are protected.

The present invention relates to the field of nuclear technology. A container for storing, transporting, and disposing of solid radioactive waste comprises a canister made of reaction-sintered silicon carbide with a free silicon content of 3% to 30% by weight, with a fumed silicon carbide layer deposited on the canister's surface. The canister's outer layer is made of metal foam with an open porosity of 60% to 70% and a pore size of 5 mm to 6 mm. The pores are filled with dispersed boron carbide powder of 40 to 50 μm in diameter, thereby protecting the environment from nuclear radiation emitted by high-level radioactive waste. A stainless steel cylinder with a thickness of 1 mm to 1.5 mm, intended to contain radioactive waste, is placed within the silicon carbide canister. A 5 mm gap between the inner surface of the silicon carbide canister and the stainless steel cylinder is filled with boron carbide powder, thereby protecting the environment from nuclear radiation emitted by high-level radioactive waste. The silicon carbide canister is sealed with a lid made of silicon carbide using a reaction welding method. The metal foam used as the metal foam with an open porosity is selected from the group consisting of titanium, aluminum, and copper. The present invention can increase the strength of containers for solid radioactive waste.