1074results about "Portable shielded containers" patented technology

The present invention relates to assemblies and method for obtaining a container comprising 212Pb on the walls obtained from a 212Pb precursor isotope source. The invention provides an improved system and method for producing 212Pb in high purity without the need for processing, with high yields, and which safely and efficiently can be transported to the locations where it is to be used.

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.

The present invention relates to assemblies and method for obtaining a container comprising 212Pb on the walls obtained from a 212Pb precursor isotope source. The invention provides an improved system and method for producing 212Pb in high purity without the need for processing, with high yields, and which safely and efficiently can be transported to the locations where it is to be used.

The invention relates to a plate type new fuel assembly transportation container which comprises a hollow cylindrical barrel, a first shock absorber, a second shock absorber, a first cover and a second cover, and the barrel is used for containing a new fuel assembly to be transported; the first shock absorber and the second shock absorber are arranged at the two ends of the cylinder in a sleeving mode respectively, and a multi-layer heat insulation structure and a steel pipe and steel plate wrapping design are adopted. The first cover body and the second cover body are located on the inner side of the top of the barrel to form a double-layer containing structure. The internal buffer assembly comprises a buffer gasket, a fireproof cloth sleeve and an accelerometer mounting part, provides dual protection for the fuel assembly, and meanwhile, dynamic changes in the transportation process are detected through an accelerometer to ensure that the fuel assembly is intact. The transportation container provided by the invention has excellent shock absorption, heat insulation and inclusiveness, is suitable for safe transportation of the plate-type new fuel assembly, and has a wide application prospect in the field of nuclear fuel transportation.

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 embodiment of the present application provides a buffer device for a spent fuel transport container and a spent fuel transport container. The buffer device includes: a base body made of wood and an outer coating for covering the surface of the base body. The base body includes: a central column, which has a first end face perpendicular to the axial direction and a second end face opposite to the first end face; a central ring body, which is arranged on the radial outer side of the central column, and has a third end face perpendicular to the axial direction and a fourth end face opposite to the third end face, the third end face is located on the same side as the first end face and the third end face is arranged flush with the first end face; the fourth end face is located on the same side as the second end face and the second end face protrudes outward from the fourth end face; a first end ring body, which is connected to the third end face, and the inner diameter of the first end ring body is larger than the inner diameter of the central column. The central column, the central ring body and the first end ring body jointly define a receiving groove for accommodating one end of the container body of the spent fuel transport container.

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 utility model provides a steering transportation device for a sealed transportation channel, and belongs to the field of nuclear technology. The device comprises a four-way channel, a rotating magnetic field generator, a rotating sling mechanism, a rotating magnetic field secondary plate and an upper rotating disc, when radioactive materials are conveyed to the position of the rotating disc, the rotating magnetic field generator is started, and the rotating magnetic field generator forms a rotating magnetic field; due to the fact that the upper rotary disc is connected with the rotary lifting appliance mechanism, the upper rotary disc is driven to rotate at the same time; and the upper turntable rotates around the central axis under the action of the rotating magnetic field, so that the technical problems of complicated steering operation and complicated structural design of the nuclear material in a closed space in the prior art are solved.

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 invention relates to a transportation container for micro-reactor new fuel elements and a loading and unloading method thereof.The transportation container comprises an outer barrel, an inner barrel and an outer cover, the outer barrel and the inner barrel are coaxially arranged to form a double-layer heat insulation structure, a first interlayer of the outer barrel is filled with heat insulation materials, a second interlayer of the inner barrel is filled with air, and double fireproof heat insulation protection is constructed; due to the three-layer sealing design of the outer cover, the first inner cover and the second inner cover, the air tightness is further improved, leakage of the fuel element is prevented, and critical safety is ensured; the container is of a multi-rib-plate and shock absorber structure, the first rib plate, the third rib plate and the second rib plate improve the strength of the barrel and the strength of the outer cover respectively, the shock absorber further enhances the anti-seismic property, and transportation safety is guaranteed. The base is combined with the symmetrical check blocks, the positioning pins and the reinforcers, so that the stability and the bearing capacity of the container are enhanced. The invention further provides a simple, convenient, efficient and safe loading and unloading method which can be widely applied to transportation and storage of micro-reactor fuel elements.

Radiation shielding technologies for radioisotope battery-powered vehicles to protect computer systems and humans and increase the energy efficiency, mass efficiency, and duration capability of the vehicle during operation. A radioisotope power system includes a radioisotope power unit that emits a plurality of radiation particles. The radioisotope power system further includes a radiation shield configured to block a first radiation particle of the plurality of radiation particles. The radioisotope power system further includes a decoupling device configured to decouple the radiation shield from a vehicle. The radioisotope power unit can include one or more radioisotopes for power, propulsion, or both power and propulsion of the vehicle. The one or more radioisotopes can include an alpha emitting isotope, a beta emitting isotope, a gamma emitting isotope, or a combination thereof. The one or more radioisotopes can be for heat generation. The vehicle can be a spacecraft or an aircraft.

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.

The invention provides a damaged fuel element storage and transportation container which comprises a storage container body, the storage container body comprises a storage barrel, an inner sleeve part and a sealing part, the inner sleeve part is arranged in the storage barrel, a plurality of storage cavities are formed in the inner sleeve part, the storage cavities are used for storing damaged elements, and the sealing part is arranged in the storage barrel; the sealing plug is arranged at the top of the storage container and is used for sealing the storage barrel; the storage container is detachably arranged in the transportation container; the device has the beneficial effects that damaged elements are stored in a sealed mode through the storage container, the storage container is stored through the transportation container, double-layer protection of the damaged fuel elements is achieved, the radiation shielding performance of the damaged fuel elements can be improved, and harm to operators in the transportation process is reduced; the protection and sealing performance of the damaged fuel element is improved, the probability of leakage of the damaged fuel element in the transportation process is reduced, and the safety of operators is improved.

The invention relates to the technical field of nuclear industry, in particular to a multi-tool universal coupling system for radioactive package processing and a carrying method, and the multi-tool universal coupling system for radioactive package processing comprises a main clamping piece which comprises a claw disc and clamping fingers arranged on the claw disc; the auxiliary clamping piece comprises clamps which are used for carrying different goods or executing specific operation, and interfaces which are arranged on the clamps and are in coupling fit with the clamping fingers; when the main clamping piece cannot complete specific operation, the matched clamp is selected, the clamping fingers are in coupling connection with the connector, the specific operation is executed through the clamp, the barrel container can be safely hoisted through the design of the main clamping piece and then released through the control part, and in addition, other specific carrying operation is achieved through connection of the main clamping piece and the auxiliary clamping piece. And the time for replacing the clamp is shortened.

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 invention relates to a package comprising radioactive content and to packaging for transporting and / or storing said content, the packaging comprising an internal shock-absorption system (22) housed in the confinement chamber between the radioactive content and an axial blocking member of the chamber, the radioactive content comprising a storage device and one or more radioactive elements. The internal shock-absorption system (22) comprises a first shock-absorption device (40) for absorption by plastic deformation in order to provide shock absorption for the storage device (30), and a second shock-absorption device (50a-50f) for absorption by plastic deformation associated with a radioactive assembly formed of one or more radioactive elements, the first and second shock-absorption devices being designed to operate independently of each other and to take account of the maximum decelerations that can be withstood by the storage device and the radioactive elements accommodated in said device.

The utility model relates to the technical field of radioactive substance transportation, in particular to an outer package for transporting a uranium hexafluoride sampling container, which comprises a lower box body, an upper box body and a lower box body, the box cover is hinged to the lower box body, and an upper buffer piece is arranged in the box cover; the locking assembly is arranged on the lower box body and the box cover and used for locking the lower box body and the box cover; and the handle assembly is arranged on the lower box body. The outer package is of a box body structure which is formed by vertically hinging the box cover and the lower box body and provided with the upper plane and the lower plane, the occupied space is small, stacking is convenient, the anti-opening rod is arranged on the spring buckle of the locking assembly, the structure is simple, use is convenient, the outer package is effectively prevented from being vibrated open in the transportation process, and the transportation efficiency is improved. And the safety of the uranium hexafluoride sampling container in the transportation process is ensured.

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.