Abstract: A tamper evident safety seal includes a first band, a second band and first and second arms connecting the first band and the second band. The seal is positioned around a radiopharmaceutical container and further includes a connector assembly having a connector and a break away portion that, when separated, provides visual evidence that the seal has been broken.

Abstract: This disclosure describes an apparatus and inspection system that is useful to inspection tubes (e.g., boiler tubes). The apparatus can comprise a housing and a pair of translating baffles that engage the outside of the housing. In one embodiment, the housing moves relative to the translating baffles during rotation of the housing to change the orientation of the housing relative to the boiler tubes. The housing and the translating baffles maintain engagement to prevent radiation from leaking out of the housing and into the surrounding environment.

Abstract: In one embodiment, a neutron shielding material is formed of boron-adding stainless steel of either austenite-ferrite two-phase stainless steel or ferritic stainless steel, the austenite-ferrite two-phase stainless steel containing, in mass %, B: 0.5% to 2.0%, Ni: 3.0 to 10.0%, and Cr: 21.00 to 32.00%, the ferritic stainless steel containing, in mass %, B: 0.5% to 2.0%, Ni: 4.0% or less, and Cr: 11.00 to 32.00%, and the boron-adding stainless steel being well in ductility and thermal conduction property.

Abstract: The present invention provides compositions for the protection against electromagnetic radiation. The compositions include a polymeric material including a polyamide such as nylon 6 or nylon 6, 6, barium sulfate and magnesium sulfate. The polymeric material upon exposure to incident electromagnetic radiation emits subtle electromagnetic oscillations at probiotic frequencies that counter adverse effects of incident electromagnetic radiation. The polymeric material may be formed into a protective housing for electronic devices and may be formed into protective fabrics.

Abstract: Disclosed are the apparatus and methods for closing a canister that stores and transports spent nuclear fuel. In one embodiment, the canister includes a canister shell that includes an open end. A closure lid is inserted within the open end of the canister shell. The closure lid engages the open end of the canister shell to provide a weld area that is substantially on the outer circumference of the closure lid. The weld area includes a first weld layer and a second weld layer. The first weld layer welds the closure lid to the canister shell at the weld area and closes the canister. The second weld layer also welds the closure lid to the canister shell at the weld area, providing a redundant closure seal, and is disposed substantially on top of the first weld layer. The method for closing the canister is provided herein.

Abstract: Disclosed herein are embodiments of a radiation shielding lid of a radiation shielding container (e.g., auxiliary radiation shield) designed to house a radioisotope generator assembly.

Abstract: Method for packing nuclear fuel in a cooling pond in a canister (12) located inside a container (10), comprising the steps of the immersion of the canister (12) and the container (10), filling the canister (12), fitting a sealing device (D) comprising caps and means of attaching a cap onto said canister (12) and of checking this attachment.

Abstract: A layered barrier for a compact particle facility is provided; the layered barrier includes a first layer formed from first shielding elements and a second layer formed from second shielding elements. The first and second shielding elements are modular and have different shielding characteristics from one another.

Abstract: A method to confine a nuclear reactor fuel bundle assembly including: inserting a lower portion of the fuel bundle assembly into an open end of a lower fuel particle barrier; supporting the lower portion of the fuel bundle with the lower fuel particle barrier; grasping the lower portion of the fuel bundle assembly with the lower fuel particle barrier; lowering an upper fuel particle barrier over an upper tie plate of the fuel bundle assembly; moving at least a portion of a handle fixed to the upper tie plate through an open slot in the upper fuel particle barrier; closing the open slot with a closure device after the handle passes through the slot, and preventing fuel particles being released from the nuclear reactor fuel bundle assembly by the upper and lower fuel particle barriers.

Abstract: Radiation shielding devices are provided herein. In particular, the devices provided herein can be adapted to shield radiation emitted by one or more radioactive brachytherapy seeds contained within, for example, a vial or a cartridge.

Abstract: In one characterization, the present invention relates to a radiation-shielding assembly for holding a container having a radioactive material disposed therein. The assembly may, at least in one regard, be referred to as an elution shield and/or a dispensing shield. The assembly includes a body at least partially defining a cavity. There is at least one opening through the body into the cavity. The assembly may include a cap that at least generally hinders escape of radiation from the assembly through the opening. The cap may be releasably attached to the body in one orientation and may establish non-attached engagement with the body in another orientation. The assembly may include an adjustable spacer system for adapting the assembly for use with containers having different heights.

Abstract: A shield for absorbing radiation emitted by a target during operation of a cyclotron. The shield includes an inner box structure having a recess for receiving the target. In addition, the shield includes a first plurality of shield elements arranged in a layered configuration about the inner box structure. The shield also includes an outer box structure for receiving the inner box structure and the first plurality of shield elements. Further, a second plurality of shield elements is arranged in a layered configuration about the outer box structure. The shield elements are arranged in both horizontal and vertical orientations and are removable.

Abstract: A method for storing high level radioactive waste in a passively cooled cavity. In one embodiment, the invention comprises: (a) providing a container comprising an outer shell having an open top end and a hermetically closed bottom end, an inner shell forming a cavity, the inner shell positioned within the outer shell so as to form a space between the inner shell and the outer shell, and at least one opening in the inner shell that forms a passageway between the space and a bottom portion of the cavity; (b) lowering a hermetically sealed canister holding high level radioactive waste into the cavity via the open top end; and (c) positioning a lid having at least one inlet vent and at least one outlet vent atop the container such that the at least one inlet vent forms a passageway from an ambient atmosphere to the space and the at least one outlet vent forms a passageway from the cavity to the ambient atmosphere, the lid substantially enclosing the open top end.

Abstract: A shield for absorbing radiation emitted during generation of a radioisotope. The shield includes an inner portion fabricated from a first type of shielding material. The shield also includes an outer portion fabricated from a second type of shielding material wherein the outer portion serves as a mold for forming the inner portion. The inner portion may be fabricated from a material which shields against gamma rays such as concrete. The outer portion may be fabricated from a material which moderates neutrons such as high density polyethylene. Additional shielding materials may be embedded into the inner portion as desired.

Abstract: A radioactive substance storage container 100 includes a body 10 and a lid 10 having a sealed structure, and a basket 5 housed in the body 1 to hold fuel assemblies. The basket 5 includes a neutron shielding material. The radioactive substance storage container 100 includes a subcritical-performance reinforcing member 20 including a neutron shielding material and located between an inner periphery of the body 1 and an outer periphery of the basket 5.

Abstract: An inspection method and apparatus for shielding container for high-activity waste is mainly to design the inspection depth of a radiation source in a shielding container and the inspection zone outside the shielding container. It employs a sticking lifting buckle ring at the container cover bottom and a flexible pull string to hang a radiation source inside the shielding container. Between the shielding container and the container cover, there is a compression resistant tube to allow the flexible pull string to pass through and extend outside the shielding container. The flexible pull string allows descending and ascending operation of the radiation source to different height inside the shielding container. The method also includes measuring and recording surface dose rate in each inspection zone outside the shielding container. With the measured surface dose rate from each inspection zone, the method uses a radiation shielding estimation and verification procedure to determine defected shielding container.

Abstract: A holder for a vial containing a sterile liquid for use with a radiopharmaceutical elution system includes a holder body. The body has a top, an opposing bottom, an opening in the top and a vial chamber. The vial chamber extends from the opening in the top toward the bottom and is sized and shaped for receiving the vial therein. An access opening extends through the bottom to the vial chamber and is aligned with a septum of the elution vial when the sterile vial is received in the vial chamber. A cap is removably secured to the top of the holder body for selectively opening and closing the vial chamber. The holder body includes plastic and has a density less than the density of the cap.

Abstract: An arrangement for automatic handling of a radioactive material includes a shielding unit, at least one handling unit arranged inside the shielding unit, and an operating unit arranged outside the shielding unit and configured to operate the at least one handling unit. Only the handling unit or parts of the handling unit are in contact with the radioactive material. The arrangement for automatic handling of radioactive materials can be used for fully automatic process control, including physical and/or chemical operations, on radioactive fluids inside shielding. Self-shielded synthesis modules or dispensers can thus be provided for handling and processing radioactive fluids.

Abstract: A composition of matter that experiences an increase rate of radioactive emission is presented. The composition comprises a radioactive material and particles having affinity for Hydrogen or its isotopes. When exposed to Hydrogen, the composition's emission rate increases. Methods of production are also presented.

Abstract: A compressed powder composite (CPC) material for absorbing neutrons emitted from spent nuclear fuel thereby preventing the initiation of a chain reaction. The CPC material is typically provided as a substantially insoluble cylindrical pellet that is highly resistant to corrosion and is not subject to the failure modes associated with the alloy materials typically used in neutron absorption materials. The pellet preferably includes a dendritic nickel powder substantially uniformly mixed with a neutron absorber powder material, preferably boron carbide. Tubes filled with CPC materials, such tubes for replacing control roads so that a spent nuclear fuel assembly may be disposed of substantially indefinitely.

Abstract: A container for a vial of radiopharmaceutical, made of polymethyl methacrylate consists of a receptacle, with a cavity capable of containing the vial of radiopharmaceutical, and of a lid screwed onto the receptacle for closing the container, said lid presenting a central through-hole. A set, in combination with this container with the vial of radiopharmaceutical, consisting of a bottle of saline solution and two infusion catheters, enhances the radioprotection during the infusion of a radiopharmaceutical in an infusion operation.

Abstract: In one characterization, the present invention relates to a radiation-shielding assembly for holding a container having a radioactive material disposed therein. The assembly may, at least in one regard, be referred to as an elution shield and/or a dispensing shield. The assembly includes a body at least partially defining a cavity. There is at least one opening through the body into the cavity. The assembly may include a cap that at least generally hinders escape of radiation from the assembly through the opening. The cap may be releasably attached to the body in one orientation and may establish non-attached engagement with the body in another orientation. The assembly may include an adjustable spacer system for adapting the assembly for use with containers having different heights.

Abstract: A pharmaceutical pig is used to transport a syringe containing a liquid radiopharmaceutical from a radiopharmacy to a medical facility for administration to a patient. The pharmaceutical pig includes an elongate polymer cap that is removably attached to an elongate polymer base. The elongate polymer cap includes a cap shell that completely encloses a cap shielding element and the elongate polymer base includes a base shell that completely encloses a base shielding element. Preferably the polymer utilized for the cap shell and the base shell is polycarbonate resin, e.g., LEXAN®. An inner liner is not utilized and the cap shielding element and the base shielding element, which are preferably, but not necessarily, made of lead, are completely sealed and unexposed.

Abstract: A method for underwater packaging of radioactive materials includes creating a vacuum in a cavity of a cleaning device to automatically cause a portion of the cleaning device to move upward to actuate the cleaning device from an open position to a closed position; mounting the cleaning device inside a safe containment area of a transportation and/or storage device; placing the transportation and/or storage device in a pool after filling the safe containment area with water; loading a radioactive material into the safe containment area; closing the transportation and/or storage device using at least one cover; extracting the transportation and/or storage device from the pool; draining the water inside the safe containment area; and creating a pressure differential in the safe containment area to dry the safe containment area, wherein the pressure differential causes the cleaning device to automatically actuate from the closed position to the open position.

Abstract: In one embodiment, a neutron shielding material is formed of boron-adding stainless steel of either austenite-ferrite two-phase stainless steel or ferritic stainless steel, the austenite-ferrite two-phase stainless steel containing, in mass %, B: 0.5% to 2.0%, Ni: 3.0 to 10.0%, and Cr: 21.00 to 32.00%, the ferritic stainless steel containing, in mass %, B: 0.5% to 2.0%, Ni: 4.0% or less, and Cr: 11.00 to 32.00%, and the boron-adding stainless steel being well in ductility and thermal conduction property.

Abstract: A spent fuel storage rack 1 according to the present invention is installed in a fuel storage pool of a nuclear facility, and has a rectangular parallelepiped shape forming a plurality of lattice-like cells 2a that are configured to separately accommodate a plurality of fuel assemblies in a matrix of rows and columns. As shown in FIG. 1, the spent fuel storage rack 1 includes: a base 17 configured to support lower parts of fuel assemblies, the base 17 forming a bottom surface of the spent fuel storage rack 1; an outer frame 3 located above the base 17, the outer frame 3 forming an outermost periphery of the spent fuel storage rack 1; and a lattice body 2 disposed inside the outer frame 3, the lattice body 2 forming the lattice-like cells 2a.

Abstract: A device containment apparatus includes a vessel for storing an explosive device and minimizing dispersal of radioactive material. The vessel includes an outer wall defining an interior area. A first frame supports the vessel and supports a first or outer radiation shield that is spaced from the vessel. A second or inner radiation shield can also be provided, supported adjacent the vessel's outer wall by a second frame that includes upper and lower frame rings. The vessel and the second radiation shield can be generally spherical, while the first frame is substantially rectangular, and the first radiation shield includes substantially planar sides.

Abstract: A nuclear reactor fuel bundle confinement system including: a fuel bundle with an upper tie plate; a channel enclosing the fuel bundle; a handle for the fuel bundle extending above the fuel bundle; an upper fuel particle barrier positioned over the upper tie plate and above the fuel rods, wherein the fuel particle barrier has a permeable panel at least co-extensive with an open area of the upper tie plate; a slot in the permeable panel through which passes the handle, and a closure device on the fuel particle barrier having a closed position which covers the slot and an open position that leaves the slot open; a lower fuel particle barrier positioned over the lower tie plate and below the fuel rods, wherein the lower portion of the fuel bundle assembly is grasped by the lower fuel particle barrier.

Abstract: The object of this invention is to provide a device and method for the dry intermediate storage of irradiated fuel elements. The apparatus includes a casing which includes tiered superposed modules made of thermally conductive material and having compartments for accommodating fuel elements with a heat sink arranged on a perforated support plate. The system includes a retaining system which includes a clearance space left between a top module of a tier and a support plate of a tier above the superposed module.

Abstract: A radiation source container comprising: a radiation source capsule (1); a radiation source holder (4) having an aperture (B) that emits unidirectionally radiation emitted from a radiation port A of the radiation source capsule, that provides screening such that no leakage of radiation takes place except from this aperture, and that fixes this radiation source capsule (1) in a manner that is difficult to attach or detach; a container (7) that accommodates the radiation source holder (4) and that has an irradiation window (C) that transmits radiation emitted from the aperture; an attenuation plate (3) provided between the radiation port of the radiation source capsule and the irradiation window, that attenuates beforehand the amount of radiation emitted; a shutter (6) provided between the attenuation plate (3) and the irradiation window (C) and that screens the radiation emitted from the irradiation window; and a capsule cover whereby, when the recommended use period in respect of the sealing performance of th

Abstract: The present invention relates to a system, method and apparatus for providing additional radiation shielding to a container holding radioactive materials. In one aspect, the invention is an apparatus that includes a tubular shell constructed of a gamma radiation absorbing material and having an inner surface that forms a cavity having an axis, the cavity having an open top end and an open bottom end; a plurality of spacers extending from the inner surface of the shell toward the axis of the cavity, the spacers extending a first height from the inner surface of the tubular shell; and one or more flange members located at or near the open top end of the cavity extending from the tubular shell toward the axis of the cavity, the flange member extending a second height from the inner surface of the shell, the second height being greater than the first height.

Abstract: There are provided: a container body (11) that has an opening in one end; a lid member (12A) that seals the opening; a prismatic pipe (30) that is arranged in the container body (11); a fuel holder (20) that covers a side surface of a fuel assembly when inserted into the prismatic pipe (30); and pressing members (37a, 37b) that are arranged on the prismatic pipe (30) and press the fuel holder (20), in the prismatic pipe (30), against inner surfaces of the prismatic pipe (30). One end (23) of the fuel holder (20) is formed in a tapered shape inclining toward an inside of the fuel holder (20). One end of the prismatic pipe (30) is provided with a first guide member (40) that has a recess (41) conforming to a shape of the one end (23) of the fuel holder (20).

Abstract: A neutron absorbing insert for use in a fuel rack and method of manufacturing the same. In ones aspect, the invention is a neutron absorbing apparatus for insertion into a fuel rack comprising: a sleeve having a first wall and a second wall, the first and second walls forming a chevron shape; and the first and second wall being a single panel of a metal matrix composite having neutron absorbing particulate reinforcement bent into the chevron shape along a crease.

Abstract: A method of loading nuclear fuel assemblies into a fuel rack in an underwater (or other submerged) environment that reduces the depth required for the pool to effectuate the fuel rack loading procedure. In one embodiment, the method comprises submerging a nuclear fuel assembly having an axis and a horizontal cross-section in a pool; providing a fuel rack in the pool, the fuel rack comprising a body structure comprising at least one elongated cell, a top, a bottom, a first lateral side, at least one elongated slot in the first lateral side that forms a lateral passageway into the cell; positioning the fuel assembly laterally adjacent to the elongated slot of the fuel rack so that the axis of the fuel assembly is substantially aligned with the elongated slot; and translating the fuel assembly in a lateral direction through the elongated slot and into the cell.

Abstract: A canister apparatus, basket apparatus and combinations thereof for transporting and/or storing high level radioactive waste, such as spent nuclear fuel. The canister apparatus comprises a cavity for receiving the spent nuclear fuel that is surrounded by two independent gas-tight containment boundaries. The structures that form the two independent gas-tight containment boundaries are in substantially continuous surface contact with one another, thereby facilitating sufficient heat removal from the cavity. In another aspect, the invention is a basket apparatus having a plurality of disk-like grates arranged in a stacked and spaced arrangement so that the cells of the disk-like grates are aligned. In still another aspect, the invention can be a basket apparatus having a disk-like grate having a ring-like structure encompassing a gridwork of beams specially arranged to achieve a unique cell configuration.

Abstract: A container for transporting a receptacle (2) containing a radioactive substance for medical use. includes a shielded body made up of a belt of side walls connected to a base element and defining a top opening, and a shielded closing lid attachable to the top opening by locking elements shaped so as to be activated by a translational movement of the lid in the top opening, this “locking movement” taking place along the axis of the opening and towards the opposing base element. The lid is further equipped with elements for deactivating the locking elements to enable it to be separated from the container body. In one advantageous embodiment, the lid has a plurality of retractable projecting studs designed to fit by a snap-action type phenomenon into at least one complementary housing formed in the opening of the container body during the locking movement.

Abstract: A containment medical apparatus for use in association with medical treatments requiring radioactive substances has a tubular housing with a cap configured for closing an open end of the tubular housing. A quick release mechanism holds the cap on an open end of the tubular housing.

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 canister for transporting/storing radioactive materials, comprising two concentric shells between which is housed a radiological protection device forming a barrier against gamma radiation, comprising a first and a second metal radiological protection components superimposed along a radial direction of the canister, the first component being supported against the outer shell and the second component being supported against the inner shell. In addition, the components are in contact with each other along an interface taking, in section along any plane integrating the longitudinal axis, the form of a straight line segment inclined in relation to this axis.

Abstract: A vessel for storing and transporting hazardous substances, like for example Uranium Hexafluoride, includes a body having an internal region that is subdivided into two or more isolated regions. The vessel further includes end members that house ingress and egress valves. A cover assembly is affixed to the vessel to shield the valves from damage due to exposure and/or impact.

Abstract: A thin film measurement technique is disclosed. The thin film measurement technique comprises radioisotopes, radiation detectors, mechanical hardware, electronics and/or circuitry, wires, cables, connectors, measurement software, and a computer. One aspect of the thin film measurement technique pertains to measurement sensors, which measure radiation emerging from material surfaces. Another aspect of the disclosure pertains to mechanical hardware that enables the thin film measurement to be made. Another aspect of the disclosure pertains to filter housings. Another aspect of the disclosure pertains to measurement software, for quantifying the measurement from the sensor, and/or controlling and optimizing processes based on said measurements. Another aspect of the disclosure pertains to hardware and equipment utilizing the thin film measurement technique. All aspects can be utilized alone or in combination with one another.

Abstract: A radiographic projector (10) for housing and projecting a radioisotope for use in radiography is described. The front end of the projector has a chamfered surface (12) for receiving an ancillary shielding component. The material used for the front end surface of the projector is tungsten powder in a less dense material matrix. A locking mechanism (30) for a projector is described, including a locking bar for locking a source holder in the projector. The locking mechanism includes an interlock section for retaining the locking bar in an unlocked position while a source holder is not in its storage position, and a latch section for latching the locking bar in the unlocked position prior to engagement of the interlock section. A holster for mounting a radio-graphic projector and a retraction cage for a remote windout mechanism are also described.

Abstract: The invention is directed to improved containers for pharmaceuticals and any tubing and tubing connectors associated therewith, particularly containers for pharmaceuticals which are irradiated, heated or otherwise subjected to increased pressure. In a preferred embodiment, the invention is directed to an improved container for use in a radioisotope generator, such as a rubidium-82 generator.

Abstract: A canister for transporting and/or storing radioactive materials, the canister comprising two concentric shells between which is housed a radiological protection device comprising at least a first and a second metal components adjacent along a circumferential direction. According to the invention, the first component is supported against the outer shell and at a distance from the inner shell, whereas the second component is supported against the shell and at a distance from the shell. In addition, the components are in contact with each other along an interface taking, in section along any plane orthogonal to the longitudinal axis and crossing this interface, the form of a straight line segment defining with a radial straight line crossing it at its centre an acute angle (A).

Abstract: The present invention provides a radiation-shielding container for a radiopharmaceutical that may be magnetically picked and placed, assembled and dis-assembled.

Abstract: The invention relates to a canister (1) for final repository of spent fuel elements from a nuclear reactor, comprising an insert (2) that contains said spent fuel elements, an inner copper casing (4a, 4b, 4c) that encloses the insert (2), and at least one outer casing (5a, 5b, 5c) that encloses the copper casting and that consists of a passive-film-forming metal or metal alloy, the passive film on the casing being constituted by an essentially oxidic film that is rich in one or more of the metals in the group of metals that consist of the metals zirconium, chromium and titanium.

Abstract: In one characterization, the present invention relates to a radiation-shielding assembly for holding a container having a radioactive material disposed therein. The assembly may, at least in one regard, be referred to as an elution shield and/or a dispensing shield. The assembly includes a body at least partially defining a cavity. There is at least one opening through the body into the cavity. The assembly may include a cap that at least generally hinders escape of radiation from the assembly through the opening. The cap may be releasably attached to the body in one orientation and may establish non-attached engagement with the body in another orientation. The assembly may include an adjustable spacer system for adapting the assembly for use with containers having different heights.

Abstract: In one characterization, the present invention relates to a radiation-shielding assembly for holding a container having a radioactive material disposed therein. The assembly may, at least in one regard, be referred to as an elution shield and/or a dispensing shield. The assembly includes a body at least partially defining a cavity. There is at least one opening through the body into the cavity. The assembly may include a cap that at least generally hinders escape of radiation from the assembly through the opening. The cap may be releasably attached to the body in one orientation and may establish non-attached engagement with the body in another orientation. The assembly may include an adjustable spacer system for adapting the assembly for use with containers having different heights.

Abstract: In one characterization, the present invention relates to a radiation-shielding assembly for holding a container having a radioactive material disposed therein. The assembly may, at least in one regard, be referred to as an elution shield and/or a dispensing shield. The assembly includes a body at least partially defining a cavity. There is at least one opening through the body into the cavity. The assembly may include a cap that at least generally hinders escape of radiation from the assembly through the opening. The cap may be releasably attached to the body in one orientation and may establish non-attached engagement with the body in another orientation. The assembly may include an adjustable spacer system for adapting the assembly for use with containers having different heights.

Abstract: In one characterization, the present invention relates to a radiation-shielding assembly for holding a container having a radioactive material disposed therein. The assembly may, at least in one regard, be referred to as an elution shield and/or a dispensing shield. The assembly includes a body at least partially defining a cavity. There is at least one opening through the body into the cavity. The assembly may include a cap that at least generally hinders escape of radiation from the assembly through the opening. The cap may be releasably attached to the body in one orientation and may establish non-attached engagement with the body in another orientation. The assembly may include an adjustable spacer system for adapting the assembly for use with containers having different heights.