561results 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 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 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.

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.

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.

The utility model discloses a radioactive waste storage cabinet which comprises a bottom plate, a surrounding plate and a front baffle are installed on the upper surface of the bottom plate, and the front baffle is located on one side of the surrounding plate. A radioactive waste storage barrel and a moving assembly used for moving the radioactive waste storage barrel are arranged in a storage cavity formed among the bottom plate, the surrounding plate and the front baffle, a moving plate is arranged on the moving assembly, and a connecting plate is installed at the rear end of the upper surface of the moving plate. An electric push rod used for pushing the moving plate to move is installed on the outer wall of one side of the connecting plate, and the other end of the electric push rod is installed on the inner wall of one side of the surrounding plate. According to the radioactive waste storage device, a worker can conveniently move the radioactive waste storage barrel out of the storage cavity or place the radioactive waste storage barrel into the storage cavity, the moving height of the radioactive waste storage barrel when the worker moves out of the radioactive waste storage barrel is reduced, the labor intensity of the worker is reduced, and time and labor are saved.

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 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 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.

To provide a container (1) for transporting and / or storing a radioactive material (3), which comprises a cavity (12) for storing the radioactive material, and a radioactive protection device (14) composed of a radioactive protection element (16) arranged in an annular space (18).SOLUTION: According to the present invention, in relation to at least two contiguous radiation protection elements (16) from a longitudinal direction (8) and a circumferential direction (28) along a predetermined direction of an annular space, provided is a locking member (32) designed to limit / prevent the relative distance of the two radiation protection elements (16) in a predetermined direction.SELECTED DRAWING: Figure 8

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 invention belongs to the technical field of nuclear power, and particularly relates to a spent fuel storage module and a mounting and sampling method thereof. The storage barrels are fixedly supported on the bottom plate through the supports and the pre-embedded assemblies, the supporting stress relation does not exist between the top plate and the storage barrels any more, a discharging opening of the top plate only plays a role in limiting horizontal displacement of the storage barrels, top plate supporting is changed into bottom plate supporting, larger loads can be borne, and the installation number of the storage barrels is remarkably increased; in addition, the top plate is not stressed any more, a fixing structure at the top of the storage barrel is omitted, the size of a barrel body on the storage barrel is reduced, the storage density of the storage barrel can be further increased, and therefore an existing scarce bedrock site is utilized in an integrated and intensive mode. The support, the upper plate, the lower plate and the foundation bolt are matched to form an adjustable structure, the levelness of the storage cylinder can be adjusted and fixed, and decoupling between the levelness of the surface of the bottom plate and leveling of the storage cylinder is achieved.

The invention relates to a shock absorber of a nuclear fuel assembly transportation container, in which a shock absorption wood block is arranged at the end part of the nuclear fuel assembly transportation container and is used for shock absorption when the nuclear fuel assembly transportation container falls off, the shock absorption wood block is in a round cake shape, and the round cross section of the round cake shape is in contact connection with the nuclear fuel assembly transportation container; the petal-shaped structures are arranged in the circumferential direction of the round-cake-shaped cylindrical surface of the damping wood block, the multiple petal-shaped structures are arranged in the circumferential direction of the cylindrical surface of the damping wood block, the damping wood blocks are arranged at the two-thirds height positions of the petal-shaped structures, and the petal-shaped structures are filled with EVA foam. According to the shock absorber, the purposes that energy is absorbed when the shock absorber is subjected to low-speed impact through the petal-shaped structures protruding out of the shock absorption wood blocks, and energy is absorbed when the shock absorber is subjected to high-speed impact through the petal-shaped structures and EVA foam filled in the petal-shaped structures are achieved, and therefore the technical effect that the shock absorber gives consideration to energy absorption and shock absorption under the low-speed impact and the high-speed impact is achieved.

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.

Some aspects are generally related to gripper systems for manipulating holders and / or containers disposed therein for use with radionuclide generators. In some embodiments, the gripper system further facilitates the insertion and / or removal of a stopper from the container, which may maintain a sterility of an interior of the container before and / or after exposure of the container to radionuclides from the radionuclide generator.

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.