Abstract: Syringe shield for using a syringe that includes a barrel, a tip and a plunger when manipulating a radioactive solution. The syringe shield includes: a shield body in which the syringe is insertable, the shield body having a window; a first flange at a first open end of the syringe shield; a second flange at a second open end of the syringe shield; wherein the second flange, the shield body, and the window include radiation shielding material, and wherein the tip of the syringe is accessible by the second open end of the syringe shield and the plunger extends outside the first open end when the syringe is inserted in the syringe shield.

Abstract: Carriers for embodying radioactive seeds, as well as a device for loading and customizing brachytherapy carriers based on the principles of optimizing a more precise and predictable dosimetry, and adaptable to the geometric challenges of a tumor bed in a real-time setting. The present disclosure relates to a specialized loading device designed to enable a medical team to create a radionuclide carrier for each patient and tumor reliably, reproducibly and efficiently.

Abstract: A container for holding radioactive waste has a side wall, a floor connected to a lower end of the side wall, and a cover. A set of side-wall formations is provided at an upper end of the side wall and on an inner surface of the side wall, and a set of cover-edge formations is distributed around an outer edge of the cover and fittable with the side-wall formations. Thus, as a result of the interfitting of cover-edge formations with the side-wall formations, the cover can be or is fixedly connected to the side wall without welds.

Abstract: A container for radioactive waste including an outer Steel wall, an inner Steel wall, a layer of lead located between the two steel walls, a steel base, a steel cover, a volume of quartz sand located inside the container, at least one internal receptacle/cassette/box that is coated/surrounded/covered at least partially by the volume of quartz sand; and radioactive waste located inside the receptacle, where the internal container may be made of steel and may contain low level radioactive waste, and alternatively, the receptacle(s) may be made of ceramic material and may contain high level radioactive waste, and in one preferred embodiment, the container has an internal rack into which the internal receptacles are placed.

Abstract: Systems and methods for storing spent nuclear fuel below grade that afford adequate ventilation of the spent fuel storage cavity. In one aspect, the invention is a system comprising: a shell forming a cavity for receiving a canister of spent nuclear fuel, at least a portion of the shell positioned below grade; and at least one inlet ventilation duct extending from an above grade inlet to a below grade outlet at or near a bottom of the cavity; the inlet ventilation duct connected to the shell so that the cavity is hermetically sealed to ingress of below grade fluids.

Abstract: A system and method for storing multiple canisters containing high level waste below grade that afford adequate ventilation of the spent fuel storage cavity. In one aspect, the invention is a ventilated system for storing high level waste emitting heat, the system comprising: an air-intake shell forming an air-intake cavity; a plurality of storage shells, each storage shell forming a storage cavity; a lid positioned atop each of the storage shells; an outlet vent forming a passageway between an ambient environment and a top portion of each of the storage cavities; and a network of pipes forming hermetically sealed passageways between a bottom portion of the air-intake cavity and at least two different openings at a bottom portion of each of the storage cavities such that blockage of a first one of the openings does not prohibit air from flowing from the air-intake cavity into the storage cavity via a second one of the openings.

Abstract: System for storing radioactive materials comprising: —a canister (4) containing radioactive waste; —a container (C), provided with a casing (1), a base (2) and a cover (3), and a passive helicoidal convection-based ventilation system provided with: lower air inlets (5); an area (6) of air circulation between the canister (4) and the inner surface of the container (C), and upper air outlets (7); the inlets (5) and outlets (7) have a decreasing variation of section in the direction of air circulation, are curved and facing an oblique direction with respect to the radial direction of the container, the air between said inlets (5) and outlets (7) describing an upward helicoidal path around the capsule or canister (4).

Abstract: Various methods and systems are provided for a radiation shielding component including a plurality of parts fused together by metal infiltrated through junctions between adjacent, interconnected parts. In one embodiment, members on a side of a panel may be interlocked with indentations on a side of another and then metal may be infiltrated through a junction between the two panels to fuse the adjacent panels.

Abstract: A nuclear waste cask with impact protection includes impact limiters detachably coupled to opposite ends of the cask. Each impact limiter may comprise a deformable energy-absorbing perforated sleeve of cylindrical shape comprising an array of closely-spaced longitudinally elongated perforations. The perforations may comprise longitudinal passages having a circular cross-sectional shape in certain embodiments. The perforated sleeve may have an annular metallic body of monolithic unitary structure in which the perforations are formed and a central opening to receive the ends of the cask therein. When exposed to external impact forces such as created by dropping the cask, the perforations collapse inwards in the impact or crush zone to absorb the energy of fall while preventing or minimizing any forces transmitted to the cask to maintain the integrity of waste containment barrier.

Abstract: A system for storing nuclear fuel, the system including a storage rack and a bearing pad. The storage rack includes an array of cells, each cell configured to receive and store nuclear fuel rods, a base plate configured to support the array of cells, and a support structure configured to support the base plate and to allow cooling fluid to circulate under and up through apertures in the base plate. The bearing pad is coupled to the support structure and is configured to limit lateral movement of the storage rack independent from lateral movement of the bearing pad. The base plate defines a base plate profile in a horizontal plane of the base plate, and the bearing pad defines a bearing pad profile in the horizontal plane of the base plate, wherein the bearing pad profile extends outside of the base plate profile.

Abstract: Infusion system configurations and assemblies facilitate routing of infusion circuit tubing lines. Tubing lines are routed into and out from compartments of a shielding assembly for the infusion system, at locations which prevent kinking and/or crushing of the lines, and/or provide for ease in assembling the circuit. A plurality of the lines may be held together by a support frame to form a disposable infusion circuit subassembly, that can further facilitate routing of the lines.

Abstract: A shielding assembly for an infusion system includes a plurality of compartments and a door for each compartment, and provides a radioactive radiation barrier for the compartments. One of the compartments contains a radioisotope generator of the infusion system and another of the compartments may contain a waste bottle of the infusion system. An opening into each of the generator and waste bottle compartments may be oriented upward, and the opening into the latter may be at a higher elevation than the opening into the former, for example, to facilitate independent removal and replacement of each. A door of at least one of the compartments, other than the generator compartment, when closed, may prevent the door of the generator compartment from being opened. A cabinet structure for the infusion system may enclose the shielding assembly and secure the generator.

Abstract: A concrete cask enabling suppression of occurrence of stress corrosion cracking (SCC) in a lid welded part of a canister. The concrete cask includes: a metal canister accommodating spent fuel; a concrete container body for accommodating the canister inside the container body; a cooling passage provided between the external peripheral surface of the canister and the internal peripheral surface of the container body, and allowing air for cooling the external peripheral surface of the canister to pass; and a top space provided between the top surface part of the canister, and the inside of a lid of the container body. A baffle plate for suppressing introduction of air rising through the cooling passage to the top space is provided.

Abstract: A module for storing high level radioactive waste includes an outer shell, having a hermetically closed bottom end, and an inner shell forming a cavity and being positioned inside the outer shell to form a space therebetween. At least one divider extends from the top to the bottom of the inner shell to create a plurality of inlet passageways through the space, each inlet passageway connecting to a bottom portion of the cavity. A plurality of inlet ducts each connect at least one of the inlet passageways and ambient atmosphere, and each includes an inlet duct cover affixed atop a surrounding inlet wall, the inlet wall being peripherally perforated. A removable lid is positioned atop the inner shell and has at least one outlet passageway connecting the cavity and the ambient atmosphere, the lid and the top of the inner shell being configured to form a hermetic seal therebetween.

Abstract: The present disclosure, in an embodiment, is a facility that includes a device configured to generate a beam having an energy range of 5 MeV to 500 MeV, a first radiation shielding wall surrounding the device, a second radiation shielding wall surrounding the first radiation shielding wall, radiation shielding fill material positioned between the first radiation shielding wall and the second radiation shielding wall forming a first barrier. In embodiments, the radiation shielding fill material includes at least fifty percent by weight of an element having an atomic number from 12 to 83, and a thickness of the first barrier is 0.5 meter to 6 meters.

Abstract: Techniques for storing nuclear waste include placing a plurality of nuclear waste portions into an inner volume of a housing of a nuclear waste canister configured to store the nuclear waste portions in a hazardous waste repository of a directional drillhole formed in a subterranean formation; substantially filling voids within the inner volume and between the plurality of nuclear waste portions with a solid or semi-solid granular material; and sealing the inner volume of the nuclear waste canister to enclose the plurality of nuclear waste portions and the solid or semi-solid granular material.

Abstract: An EUV light generator including the following components: A. an electron storage ring including a first linear section and a second linear section; B. an electron supplier configured to supply the electron storage ring with an electron bunch; C. a high-frequency acceleration cavity disposed in the first linear section and configured to accelerate the electron bunch in such a way that a length Lez of the electron bunch satisfies “0.09 m?Lez?3 m;” and D. an undulator disposed in the second linear section and configured to output EUV light when the electron bunch enters the undulator.

Abstract: In general, radiation shielding systems that shield radiation from multiple directions are described. In one embodiment, a method of shielding radiation is provided, including supporting a shielding device on an object proximate a radiation source, positioning a first shielding portion in a vertical position relative to the object, positioning a second shielding portion to extend away from the first portion, the second shielding portion attached to the first portion, and shielding radiation from the radiation source by the first shielding portion and the second shielding portion such that the first and second shielding portions provide a radiation shielding zone for a healthcare practitioner.

Abstract: A nuclear fuel storage cask includes an outer shell having a length extending from a first end to a second end of the outer shell, the outer shell defining an inner cavity circumscribed by the outer shell, an outer perimeter extending around the outer shell, an inner perimeter positioned inward from the outer perimeter, and a cooling circuit extending along the length of the outer shell, the cooling circuit including an inner passage, and an outer passage, a coolant positioned within the cooling circuit, where the coolant is configured to move through the inner passage, absorbing heat from the inner cavity of the outer shell, and the coolant is configured to move through the outer passage, dissipating heat through the outer perimeter of the outer shell, and a lid coupled the outer shell, where the lid covers the inner cavity of the outer shell.

Abstract: A radioactive waste container, for storing and transporting a radioactive waste, includes a container body, a cover and a water drain unit. The cover is fastened to the container body. The water drain unit is provided at the container body without protruding to an outside of the container body and configured to selectively drain water in the container body.

Abstract: A neutron absorbing apparatus, for insertion into a fuel cell storage system, includes a corner spine, a first wall and a second wall, each wall being affixed to the corner spine to form a chevron shape. Each wall includes an absorption sheet affixed to the corner spine, each absorption sheet being formed of a metal matrix composite having neutron absorbing particulate reinforcement, and a guide sheet affixed to and covering a fractional upper portion of the absorption sheet and extending over a top of the absorption sheet. The absorption sheet extends along the corner spine a greater length than the guide sheet.

Abstract: The invention concerns a package for transporting and/or storing radioactive materials. The package comprises a wall element (26) and a cooling element (31, 32) attached to the wall element (26) and protruding from the wall element (26) towards the outside of the package. The cooling element (31, 32) comprises a base (40) and at least one fin (35) rigidly connected to the base (40). The base (40) extends to either side of the fin (35) respectively towards two opposing lateral ends of the base, each of the lateral ends being attached to the wall element (26) via a weld.

Abstract: A ventilated apparatus for storing and/or transporting high level radioactive waste. In one aspect, the invention is a ventilated apparatus comprising: an overpack body having an inner surface forming a cavity about a longitudinal axis. A bottom portion of the overpack body is formed by a plurality of segments. Each of the segments extends from a first end wall having a projection to a second end wall having a channel. The segments circumferentially surround a longitudinal axis and are arranged in an intermeshing and spaced-apart configuration such that the projections of the first end walls of the segments project into the channels of the second end walls of adjacent ones of the segments, thereby forming inlet ducts between adjacent ones of the segments. The inlet ducts form air inlet passageways from the external atmosphere to a bottom portion of the cavity.

Abstract: A system for storing nuclear fuel assemblies includes a plurality of cells housed within a support structure. A first cell may house a first fuel assembly and a second cell may house a second fuel assembly. A plurality of compartments separate the plurality of cells and provide passageways for coolant entering a bottom end of the support structure to remove heat from the nuclear fuel assemblies. A first perforation transfers coolant between the first cell and one or more of the compartments, and a second perforation transfers coolant between the second cell and the one or more compartments. At least a portion of the coolant entering the bottom end of the support structure is transferred between the plurality of cells and the plurality of compartments. Two or more fuel storage racks may be stacked together in alternating fuel patterns to facilitate cooling the fuel assemblies with liquid or air.

Abstract: Injection device for dispensing a medicament, comprising: a cartridge module, a dispensing mechanism which is actuated to dispense the injectable preparation, a dose-setting mechanism for setting the dose at which the injectable preparation is dispensed when the dispensing mechanism is actuated, the dose-setting mechanism comprising: a housing part (11) in which at least part of the dispensing mechanism is received, a display sleeve (13) rotatable therein, and an insertion sleeve (15) that can be inserted into the housing part (11), wherein the insertion sleeve (15) has, on its outer face, a raised surface section (20) that is transparent at least in some areas, and the housing part (11) has a recess (25) which is open at its distal edge (24) and which receives the insertion sleeve (15) in a rotationally fixed manner from the direction of the open end of the recess (25), and insertion sleeve for an injection device, dose-setting mechanism for an injection device for dispensing a medicament, and method for

Abstract: A breaker valve assembly for a nuclear reactor containment includes a valve body, a valve body insert, and a lid. The valve body includes a first side wall defining a chamber, a first opening in a top portion of the first side wall, and a second opening in a bottom portion of the first side wall. The second opening communicates with the first opening of the valve body. The valve insert body includes a second side wall defining a second chamber, and a third opening in a bottom portion of the second side wall. The valve insert body is nested in the valve body. The lid is arranged on an upper edge of the side wall of the valve insert body. The valve insert body is configured to move substantially vertically with respect to the valve body.

Abstract: The present invention provides a system and method for reclaiming energy from the heat emanating from spent nuclear fuel contained within a canister-based dry storage system. The inventive system and method provides continuous passive cooling of the loaded canisters by utilizing the chimney-effect and reclaims the energy from the air that is heated by the canisters. The inventive system and method, in one embodiment, is particularly suited to store the canisters below-grade, thereby utilizing the natural radiation shielding properties of the sub-grade while still facilitating passive air cooling of the canisters. In another embodiment, the invention focuses on a special arrangement of the spent nuclear fuel within the canisters so that spent nuclear fuel that is hotter than that which is typically allowed to be withdrawn from the spent fuel pools can be used in a dry-storage environment, thereby increasing the amount energy that can be reclaimed.

Abstract: A spent nuclear fuel storage facility. In one embodiment, the invention is directed to a storage facility including an array of storage containers. Each of the storage containers includes a body portion and a lid. The body portion has a storage cavity configured to hold a canister containing spent nuclear fuel. The lid, which may rest atop the body portion in a detachable manner, includes an inlet vent and an outlet vent. Each of the storage containers may be configured to draw air through the inlet vent and into the storage cavity where the air is warmed and passed through the outlet vent as heated air. The body portion of the storage containers may be positioned below grade and the lid of the storage containers may be positioned above grade.

Abstract: A system for storing and/or transporting high level radioactive waste, and a method of manufacturing the same. In one aspect, the invention is a ventilated vertical overpack (“VVO”) having specially designed inlet ducts that refract radiation back into the storage cavity. A clear line-of-sight does not exist through the inlet ducts and, thus, the canister can be supported on the floor of the VVO. Also disclosed is a method of manufacturing a variable height VVO that falls within a regulatory license previously obtained for a shorter and taller version of the VVO.

Abstract: The invention relates to a storage device for storing and/or transporting nuclear fuel assemblies, which includes recesses (2) defined by separating partitions (9) defining first and second recesses (2), the partition comprising: two first walls (22) defining the first and second recesses and made of an aluminium-alloy material which is free of neutron-absorbing elements, and defining therebetween a first inter-wall space (28); two second walls (30) arranged in the first space (28) and made of a material which comprises neutron-absorbing elements, the distance between the inner (36) and outer (34) surfaces of each second wall (30) defining a thickness (e2), and a distance (E) being defined between the outer surface (34) of each second wall and a median partition plane (20), the values meeting the condition 0.1?e2/E?0.43.

Abstract: Improved heat transfer from an x-ray tube can be accomplished with a heatsink surrounding at least part of an x-ray tube. The heatsink can be electrically connected to an anode of the x-ray tube and can be an electrical current path. The heatsink can include a plurality of protrusions extending radially outward from the x-ray tube and can be a single, integral substance extending from an inner-surface of the heatsink to a distal-end of the protrusions.

Abstract: The present disclosure relates generally to the field of drug delivery. In particular, the present disclosure relates to a drug delivery system that includes a sealed and sterile fluid path attached to a drug-loaded container. The disclosure further relates to methods for sterilizing a portion of the drug delivery system without exposing the drug-loaded container to harmful sterilization parameters.

Abstract: A container system for radioactive waste and method for using the same is provided. The system includes a canister configured for holding radioactive waste and a lid system. In one embodiment, the lid system comprises a two-part lid assembly including a confinement lid and a shielded lifting lid. The confinement lid is detachably mounted to the confinement lid. In use, the lifting lid supports the confinement lid for lifting and placement on the canister. The lifting lid further shields operators while the confinement lid is mounted to the canister. Thereafter, the lifting lid is removed and may be reused for confinement lid mountings on other canisters. In one embodiment, the confinement lid is bolted to the canister. The canister may be disposed in a protective overpack for transport and storage.

Abstract: Improved heat transfer from an x-ray tube can be accomplished with a heatsink surrounding at least part of an x-ray tube. The heatsink can be electrically connected to an anode of the x-ray tube and can be an electrical current path. The heatsink can include a plurality of protrusions extending radially outward from the x-ray tube and can be a single, integral substance extending from an inner-surface of the heatsink to a distal-end of the protrusions.

Abstract: Disclosed is a correction container of a Marinelli, wherein a first groove is formed in the lower portion of the container body formed with a diameter corresponding to the inner diameter of the lower surface of the Marinelli beaker, to be attached to a detector of a detecting system for nuclide analysis, a second groove having a diameter smaller than that of the first groove is formed on the upper portion, and an intake and exhaust hole is formed through the first groove to the second groove. According to the present invention, a Marinelli beaker covers a upper portion of a container body to wrap around it, and a detector of a nuclide detecting device is inserted into a first groove formed in a lower portion of the container body. By means of the correction container according to the present invention, the distance between the position of radionuclides in the sample in a Marinelli beaker and the detector is maintained constant.

Abstract: A ventilated system for storing high level radioactive waste, such as used nuclear fuel, in a below-grade environment, in one embodiment, the invention is a ventilated system comprising an air-intake shell and a plurality of storage shells that are interconnected by a network of pipes configured to achieve double redundancy and/or improved air delivery. In another embodiment, the invention is a ventilated system that utilizes a mass of low level radioactive waste contained in a hermetically sealed enclosure cavity, the low level radioactive waste providing radiation shielding for high level radioactive waste stored in a storage cavity of said ventilated system.

Abstract: A method for detecting gas leakage from a radioactive material sealed container includes measuring a temperature at a top portion of a metallic sealed container, a temperature at a bottom portion of a lid portion of a concrete-made storage container facing the top portion of the metallic sealed container, or a temperature of a member existing between the bottom portion of the lid portion and the top portion of the metallic sealed container. An inner temperature of the lid portion of the concrete-made storage container is also measured. Presence of leakage of inactive gas is estimated by comparing the temperatures.

Abstract: A precision fabrication form system for preparing a poured-concrete (with upwardly projecting anchor bolts) footing for anchorably supporting the base of an elongate, upright, structural-frame column. The system includes a reversibly stackable plurality of independent, intercooperative, fabrication-form templates—grade, pedestal, base-plate, anchor-bolt and centerline—reversibly assembleable in a predetermined stack order above a prepared ground excavation into which concrete pouring to be associated with such a footing is to occur, certain ones of these templates being infinitely adjustable relative to one another and to the ground in both pre-pour and post-pour conditions to accommodate staged, precision, X-axis, Y-axis, Z-axis, and pitch, roll and yaw axes dispositions for the concrete and anchor bolts in such a footing.

Abstract: A canister apparatus, basket apparatus and combinations thereof for transporting and/or storing high level radioactive waste, such as spent nuclear fuel. In one embodiment, the invention can be a basket apparatus for supporting a plurality of spent nuclear fuel rods within a containment structure, the basket apparatus comprising a plurality of disk-like grates, each disk-like grate having a plurality of cells formed by a gridwork of beams; and means for supporting the disk-like grates in a spaced arrangement with respect to one another and so that the cells of the disk-like grates are aligned.

Abstract: This disclosure pertains to a holder for a radioactive source capsule with pivoting first and second parts, with redundant mechanisms for retention of the capsule during transportation and handling. These retaining mechanisms include a set screw in the first pivoting part to engage the capsule and to prevent radial movement of the capsule, a locking shelf in the second pivoting part to fix the axial orientation of the pivoting bottom end of the capsule holder, and a capture tooth within the capsule to prevent release of the capsule while in the shipping and/or handling tube of the capsule holder.

Abstract: Packaging for transporting and/or storing radioactive material, comprising a packaging body which defines therein a cavity for housing radioactive material, and at least one shock absorber which is mounted on the outside of the packaging body, which has an outer surface provided with at least one first outer surface and one second outer surface which are separated by an edge that is covered by the shock absorber. The absorber comprises a metal damping structure comprising a first recess having an imaginary straight line extending therethrough, the line passing through both a center of gravity of the packaging and a point on the edge, a second recess arranged so as to face one of the outer surfaces, and a metal wall for absorbing shocks by plastic deformation. The wall is at least 5 mm thick and defines the first and second recesses on either side thereof.

Abstract: Systems and methods for storing spent nuclear fuel below grade that afford adequate ventilation of the spent fuel storage cavity. In one aspect, the invention is a system comprising: a shell forming a cavity for receiving a canister of spent nuclear fuel, at least a portion of the shell positioned below grade; and at least one inlet ventilation duct extending from an above grade inlet to a below grade outlet at or near a bottom of the cavity; the inlet ventilation duct connected to the shell so that the cavity is hermetically sealed to ingress of below grade fluids.

Abstract: A robust, durable, easy to use, reusable shipping container is disclosed that is capable of protecting contents from surrounding high temperatures up to 1000 degrees Fahrenheit for a minimum of at least three and a half hours. The container includes an inner chamber surrounded by an outer chamber. A phase change liquid (PCL) is sequestered in a porous support matrix contained in the inner chamber, while the outer chamber is filled with high temperature insulation, forming an outer barrier layer that is designed to reduce heat flux into the inner chamber.

Abstract: A biological fluids concentration device, including a tube-in-tube assembly, is disclosed. The tube-in-tube assembly receives biologic fluids and may then be placed in the bucket of a centrifuge and spun to separate out the components of the biological fluid by their various densities. For example, whole blood may be centrifuged in the tube-in-tube assembly for separating into plasma, red blood cell component, and a buffy coat. A piston slideably and sealingly engages an inner tube of the tube-in-tube assembly, the inner tube fitting within an outer tube. A lid is designed to engage the top of the outer tube, which lid has an opening therein for receipt of a plunger. The plunger is adapted to move up and down with respect to the lid and the tubes, so as to sealingly, in a down position, and unsealingly, in an open position, engage the top of the inner tube of the tube-in-tube assembly.

Abstract: Various embodiments of a decay heat conversion to electricity system and related methods are disclosed. According to one exemplary embodiment, a decay heat conversion to electricity system may include a spent fuel rack configured to pressurize spent fuel bundles to obtain superheated vapor to drive a turbine-driven pump and fast alternator all submerged with the spent fuel rack and positioned at the bottom of the spent fuel pool for conversion of electricity distributed outside of the spent fuel pool via cables without impairing spent fuel pool operations.

Abstract: To provide a containment cask for storage or transport of radioactive material, without employing a homogenization treatment. Pouring a molten lead between an inner shell 2 and an intermediate shell 3 to serve as a gamma ray shielding material, allowing the lead to cool, and subsequently, filling either one or both of a first void layer 9a formed at a boundary between the inner shell 2 and the poured lead 5a or a second void layer 9b formed at a boundary between the intermediate shell 3 and the poured lead 5a, using a low melting point metal 10 in a closely adhering state. To provide the cask 1 with a good heat-dissipating effect, by filling the void layers 9a, 9b that prevent the cask 1 from dissipating heat, with the low melting point metal 10 that has a superb thermal conductivity.

Abstract: A spent fuel storage rack that accommodates and stores spent fuels in a large number of cells formed in a grid pattern includes a flat rectangular plate-shaped base forming the bottom of the rack, columnar members extending upward from the four corners of the base, and at least a pair of upper and lower grid-shaped frame plates disposed above the base and fixed to and supported by the columnar members. Each of the cells is formed by assembling metal plates to which boron is added to a density greater than 1% into a polygonal tube, and the cells are arranged contiguously at fixed intervals in the grid-shaped frame plates.

Abstract: An apparatus for fastening a pressure vessel of a vehicle is arranged to fix the pressure vessel to a vehicle body, where the pressure vessel includes a cylindrical body, dome-shaped curved portions at both ends of the cylindrical body, and bosses at distal ends of the curved portions. The apparatus is arranged to receive the pressure vessel, and further includes: elastic bodies disposed along circumferences of the curved portions of the pressure vessel to support surfaces of the curved portions and to be disposed on a virtual flat cross section vertically crossing the curved portions along the circumferences of the curved portions to support the curved portions of the pressure vessel in all directions; and a fixed structure having one side connected to the elastic bodies and the other side connected to the vehicle body.

Abstract: Disclosed is a nuclear power plant container structure, the structure comprising: a hollow structure having a plurality of cells, each having a hollow portion therein, which are partitioned by cell walls and air-ranged in a three-dimensional pattern so as to form an empty space for sealing and storing the radioactive waste therein; a cladding for surrounding the outside of the hollow structure; and a filler selectively filled into the hollow portions of the cells for suppressing nuclear reactions of the radioactive waste or blocking radioactivity radiated from the radioactive waste.

Abstract: The invention relates to a method of loading radioactive elements (8) in a package comprising the following steps: (a) placement of a plurality of radioactive elements (8) in a storage basket (30) provided with radiological protection means (32), in the pool; (b) extraction of the basket (30) containing the radioactive elements (8) out of the pool; and (c) loading said basket (30) containing the radioactive elements (8), into the package.