319results 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.

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 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.

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.

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 discloses a radiopharmaceutical delivery box, which relates to the radiopharmaceutical transfer field and comprises a box body, the box body comprises an upper cylinder, the top of the upper cylinder is in threaded connection with a top cover, a handle belt is fixed on the outer wall of the curved surface of the top cover, a lower cylinder is movably assembled at the bottom end of the upper cylinder, and a pressurizing component is fixed on the inner wall of the upper cylinder; a receding ring groove is reserved in the inner wall of the upper cylinder, a lining cylinder fixed to the bottom end of the upper cylinder is arranged in the receding ring groove in a sleeved mode, and a plurality of sets of guide grooves are formed in the outer wall of the curved surface of the lining cylinder. Through the arrangement of the split structure of the upper barrel and the lower barrel, the radiopharmaceutical storage barrel can be adjusted according to the size of a radiopharmaceutical bottle to be stored, so that the radiopharmaceutical bottle bodies of various models are met, the internal separation barrels independently store all radiopharmaceuticals and play a role in restraining, the phenomenon that all the radiopharmaceuticals are exposed during taking and placing is prevented, and the radiopharmaceutical storage barrel is convenient to use. And the radioactive medicine bottle can be better stored.

The utility model discloses a transport container for radioactive waste barrels, which comprises a top cover, a barrel body and a base, the barrel body is mounted above the base, the top cover is mounted above the barrel body, the top cover is used for sealing the barrel body, and the radioactive waste barrels are placed in the barrel body. The top cover comprises a cover body and a lifting part above the cover body, the lifting part is used for lifting the top cover, and a plurality of long slotted holes are formed in the cover body; the barrel body comprises a barrel body, a barrel body flange plate, a positioning rib plate, a wrap angle and a plurality of lifting lugs, the barrel body flange plate is fixed at the top end of the barrel body, the barrel body flange plate and the cover body are connected at any angle through a long slotted hole by using a bolt, the positioning rib plate is arranged at the lower end of the inner side wall of the barrel body, the wrap angle is arranged on the outer side of the barrel body flange plate, and the lifting lugs are fixed on the outer side of the barrel body; the base comprises a base plate and a plurality of forklift grooves, and the forklift grooves are fixed below the base plate. The transportation container is safe, stable, easy to load and transport, shockproof and capable of being integrally transferred.

The embodiment of the invention provides a radioactive source reversing device and a radioactive source reversing method. The radioactive source reversing device comprises a first storage tank, a second storage tank, an operation rod and an adsorption assembly. The operating rod is provided with a holding end and an operating end, the adsorption assembly is arranged at the operating end, and the adsorption assembly adsorbs the radioactive source so that the radioactive source can be selectively stored in any one of the first storage cavity and the second storage cavity. According to the radioactive source reversing device, the radioactive source can be firmly adsorbed through the adsorption assembly, the stability is high, the falling risk of the radioactive source in the transferring process can be greatly reduced, and therefore the fixing effect on the radioactive source can be improved.

The present disclosure provides a ray protection device and a radiation inspection system. The ray protection device comprises: a mobile bearing device, including a vehicle frame and a traveling device supporting the vehicle frame to drive the vehicle frame to travel in a first direction; and a protection wall, arranged on the vehicle frame and including a movable wall which is movable relative to the vehicle frame. The movable wall has a shielding position and a retracting position; at the shielding position of the movable wall, the protection wall has first projection area in a vertical plane parallel to the first direction; and at the retracting position of the movable wall, the protection wall has second projection area in the vertical plane, where the first projection area is larger than the second projection area.

A system for the production of a radioisotope comprising a container (1), which has a planar face (4) on which a portion of solid target material (M) is present having an elliptical shape, an irradiation station (35) for emitting a proton beam (B) against the portion of solid target material (M) in the container (1) and a transfer system (37) for transferring the container (1) to the irradiation station (35). The irradiation station (35) has an annular seat (39), which is suitable for coaxially receiving the container (1) from the side of the planar face (4) and is oriented obliquely with respect to the proton beam (B) in such a way that a section (S) of the proton beam (B) along a plane of the annular seat (39) is elliptical. The transfer system (37) comprises a housing (42) for the container (1), a rotation assembly (43) for rotating the container (1) within the housing (42) in order to orient the elliptical shape of the solid target material portion (M) as the elliptical shape of the proton beam section (B), and a handling assembly (45) for grasping the container (1) from the side opposite the planar face (4) and transferring it from the housing (42) to the annular seat (39).

A shielding module for a radioactive waste container (C) comprising a perimeter wall (1) and a closing lid (2), which define a cavity (3) suitable for housing the container (C), and a number of metal elements (4) attached along the perimeter wall (1) and protruding into said cavity (3), said metal elements (4) forming means for limiting lateral movement, for centring and for dampening impacts against the side wall of the container (C) with respect to the shielding module (10), in the event of potential external impacts or the sideways fall of the assembly formed by the container (C) and the shielding module (10).

The application relates to the technical field of fuel assembly transportation devices and discloses a nuclear fuel assembly transportation container hook locking device which comprises connecting pieces fixed on a fuel assembly transportation container and arranged adjacently on the same side, a limiting piece, and a lock hook piece pivotally connected to the connecting pieces and detachably connected with the limiting piece; the limiting piece is provided with a limiting groove and a locking mechanism, the locking mechanism comprises a lock tongue; the lock hook piece is provided with a hooking part which can be inserted into the limiting groove and hooked to a movable door assembly; when the lock tongue is subjected to a preset size of thrust of the hooking part, the lock tongue exits the limiting groove; when the hooking part is inserted into a set position of the limiting groove, the lock tongue extends into the limiting groove and stops the hooking part. The application has the limiting effect on the circumferential freedom of the movable door assembly, solves the constraint problem of the movable door assembly during fuel assembly loading and unloading, improves the stability of the fuel assembly transportation container, and has the advantages of simple structure, convenient operation and easy maintenance.

The utility model discloses shielding case of lead boron polyethylene shielding board adaptation uses, include: shielding case body, extension part, the extension part includes support column, stand and hole body, the support column is fixed in the top of shielding board, and shielding case body is located the top of shielding board, and the hole body is seted up in the top of shielding case body, and the stand is movably connected in the inside of support column, and the upper portion of outer surface is fixedly connected in the inside of hole body. The utility model discloses the extension part of being equipped with, the design of stand can extend in the inside of support column, and the sliding cooperation of cooperation guide block and guide groove makes the operator only needs hand force to be able to with shielding case body is proposed to the upper portion and removes to the upper portion, can let the range of shielding board completely show, whether it is the placement of larger size equipment, replacement, or the maintenance to the inside large -scale component, can provide the operation space of sufficient, significantly reduce the operation difficulty, reduce the equipment collision risk caused by the operation space limitation.

The protective transportation device for the medical radiopharmaceuticals comprises a protective barrel, a protective cover and a plurality of adsorption assemblies arranged in the protective barrel, storage grooves are formed among the adsorption assemblies, the adsorption assemblies are distributed in the circumferential direction of an inner cavity of the protective barrel at equal angles, and the radial sections of the adsorption assemblies are each of a 90-degree fan-shaped structure; each adsorption assembly comprises a plurality of splicing frames, every two adjacent splicing frames are tightly attached, circulating holes are formed in the circumferential outer walls of the splicing frames, the multiple adsorption assemblies distributed in the circumferential direction at equal angles are arranged in the protection barrel, the radial section of each adsorption assembly is of a 90-degree fan-shaped structure, and the multiple adsorption assemblies are formed by stacking the multiple splicing frames; the circulation holes of the adjacent splicing frames are formed in a staggered mode to form a continuous snake-shaped airflow channel, the structure remarkably prolongs the escape path of radioactive gas, the gas is forced to undergo multiple times of steering and diffusion resistance when passing through the multiple adsorption layers, and therefore the leakage risk is effectively reduced.

The utility model discloses a radioactive source recovery tank which comprises a recovery tank body and a first quick connector, the recovery tank body is provided with a storage cavity used for storing a radioactive source, one end of the recovery tank body is provided with a water inlet communicated with the storage cavity, and the other end of the recovery tank body is provided with an opening. The first quick connector is installed at the opening of the recycling tank body in a replaceable mode through a quick connecting structure, when the first quick connector is installed at the opening of the recycling tank body, the first quick connector is provided with a filtering part, one end of the filtering part is communicated with the storage cavity, and a water outlet is formed in the end face or the side face of the first quick connector and communicated with the other end of the filtering part. And the first quick connector is mounted at the opening of the recovery tank body, so that the functions of recovering, storing, cleaning and drying the radioactive source are realized.

A container for storing high assay low enriched uranium hexafluoride (UF6) has a cylindrical lateral wall extending between first and second heads defining a container interior for receiving the radioactive material. A plurality of cylindrical poison rods extend in parallel through the container interior. Each of the poison rods has a neutron absorber. A plurality of access nozzles are situated within the first head and / or second head. Each of the access nozzles has a lateral wall defining a throughway that extends through the first head between an interior end region and an exterior end region. The interior end region captures and supports a respective end of a respective poison rod. The exterior end region is opened and closed via respectively detaching and attaching an end cap to thereby respectively expose and contain the respective poison rod.

The utility model discloses a radionuclide sealing and solidifying tank which comprises a tank body, fixing seats are arranged on the left side and the right side of the upper end of the tank body respectively, the rear ends of the two fixing seats are both fixedly connected with the front end of a connecting seat, and the radionuclide sealing and solidifying tank further comprises a sealing mechanism. The sealing mechanism comprises fixing plates, adjusting seats and adjusting grooves, the fixing plates are slidably connected into sliding grooves formed in the middles of the opposite inner side faces of the two fixing seats respectively, the adjusting seats are arranged at the lower ends of the fixing seats respectively, the adjusting grooves are formed in the lower sides of the rear ends of the adjusting seats respectively, and the sealing mechanism further comprises a pressing plate and a cover plate. The pressing plate is arranged between the ends, close to the center of the interior of the tank body, of the two fixing plates, the radionuclide sealing and solidifying tank is firm in sealing and convenient and fast to operate, a traditional sealing and fixing mode through bolt connection is replaced, and the problem that the sealing effect is reduced due to the fact that a sealing gasket is uneven in stress is solved.

This disclosure relates to the field of functional polymer composite materials technology, specifically to composite materials and their preparation methods, storage containers and their preparation methods, and preparation apparatus. The composite material is composed of epoxy resin, a curing agent, and boron carbide, wherein the mass ratio of the epoxy resin, the curing agent, and the boron carbide is 100:(20~50):(5~35); wherein the epoxy resin is a multifunctional epoxy resin, and the curing agent is a room temperature curing agent; the composite material of this disclosure possesses excellent neutron absorption capacity, significant thermal stability, good corrosion resistance, and feasible engineering implementation performance.

A system for transporting radioactive materials which may include a containment vessel, a thermal shield, and an impact limiter. The containment vessel may include a vessel body having a storage cavity for receiving radioactive materials, a lid coupled to an upper portion of the vessel body to enclose a top end of the storage cavity, and a lid seal such as a gasket positioned between the lid and the upper portion of the vessel body. The thermal shield may be positioned over the lid. The first impact limiter may be positioned over the thermal shield. The thermal shield may be resistant to high temperatures and may help to protect the integrity of the lid seal when the system is subjected to high temperatures, such as during a fire condition.

The cask (100) shields materials and passively removes heat through a heat transfer path (150) from the depths of the cask to the exterior. The path may be nonlinear heat pipes and conductive rods to ensure radiation is always shielded by the cask. Dampers (160) may surround the ends of the heat transfer path to control heat loss from the cask. A jacket (110) of fluid or meltable material that conducts heat by convection may surround the stored material and ensure a uniform temperature within the cask, and the heat transfer path may absorb heat from the jacket. The cask can be used to safely store, transport, and dispose of any heat-generating or sensitive materials. Opening and closing the cask allows for simultaneous loading and unloading of materials at a constant operating temperature provided by heaters within the cask.

The invention relates to a radioactive sampling carrier guarantee device for short-distance transportation, which comprises a box body with a multi-layer vertical stacking structure, and the multi-layer vertical stacking structure comprises a first structure layer, a second structure layer and a third structure layer which are sequentially arranged from bottom to top; an iodine adsorber is arranged in the first structure layer; the second structural layer and the third structural layer are each provided with a plurality of storage cavities, and a damping assembly is arranged in each storage cavity and used for containing a radioactive sampling carrier and buffering vibration in the transportation process; a purification fan and a power supply assembly are further arranged in the box body and form a dynamic purification module with the iodine adsorber, and at least part of the storage cavity is communicated with the dynamic purification module through an air duct to form a closed-loop purification loop; the purification fan is configured to be activated under the radiation monitoring triggering condition so as to filter and purify air in the box body.

A system is disclosed for introducing liquid radioactive waste into a vitrification melter, which vitrifies the radioactive waste. [Solution] A liquid radioactive waste injection system according to an embodiment of the present invention injects liquid radioactive waste into a vitrification melting furnace that vitrifies the radioactive waste, and may include a waste storage tank that stores the liquid radioactive waste, and a waste injection device that receives the liquid radioactive waste from the waste storage tank and injects the supplied liquid radioactive waste into the vitrification melting furnace.

The invention discloses a hanging basket device of a spent fuel transportation container. The hanging basket device of the spent fuel transportation container comprises a top plate assembly, a bottom plate assembly, a supporting plate set, a plurality of storage sleeves, a plurality of connecting rods, a plurality of limiting pieces and a plurality of fixing plate sets. In the spent fuel loading process, the hanging basket device of the spent fuel transportation container can be suitable for spent fuels of different lengths by changing the number of the fixing plate sets through the structure, and meanwhile the hanging basket device is suitable for different placement positions by replacing the supporting plate sets; therefore, the hanging basket device of the spent fuel transportation container can adapt to fuel assemblies of different types, different lengths, different burnup depths and different placement positions, the use efficiency of the hanging basket device of the spent fuel transportation container is improved, and the transportation cost of the spent fuel assemblies is reduced.

According to the invention, there is provided an overpack cask (1) for reversibly receiving, handling and transporting a repository container (100) for spent nuclear material (150), wherein the overpack cask (1) comprises a tubular cask shell (30) defining a receiving cavity (35) for reversibly receiving a repository container (100) therein, a first cask cover (10) providing a sealing closure of the receiving cavity (35) at a first axial end (31) of the tubular cask shell (30) and a second cask cover (20) providing a sealing closure of the receiving cavity (35) at a second axial end (32) of the tubular cask shell (30) opposite to the first axial end (31). At least the first cask cover (10) is removable from the tubular cask shell (30) to uncover a first opening (33) of the tubular cask shell (30) at the first axial end (31) for loading and / or unloading a repository container (100) into and from the receiving cavity (35), respectively. Furthermore, the overpack cask (1) comprises a sliding guide arrangement (40) arranged at an inner circumferential side (38) of the tubular cask shell (30) for guiding and supporting a repository container (100) during loading it into and unloading it from the receiving cavity (35), and when it is received in the receiving cavity (35).

The utility model relates to a nuclear power station spent fuel transportation container shielding protection device. The device comprises a container body; the neutron shielding layer is arranged on the outer side of the container body in a surrounding mode, a filling cavity is defined by the neutron shielding layer and the outer side wall of the container body, and the filling cavity is filled with neutron shielding materials. By arranging the neutron shielding layer surrounding the outer side of the container body and the neutron shielding material filled in the neutron shielding layer, the neutron radiation shielding problem in the spent fuel transportation and assembly loading process is solved, the neutron radiation dose on the outer surface of the transportation container can be effectively reduced, a stable shielding structure is formed, and safe transportation of spent fuel is guaranteed.

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.