Various embodiments relate to devices for transporting high-assay low-enriched uranium (HALEU). A device may include at least one section, wherein each section of the at least one section includes a number of storage tubes. Each storage tube, which is configured to receive and hold a container, extends from adjacent a first end of the section toward second, opposite end of the section. Each section further includes a number of flux traps, wherein each storage tube of the number of storage tubes is at least partially surrounded by a flux trap of the number of flux traps Associated systems are also disclosed.

A storage device for transporting and/or storing nuclear fuel assemblies is intended to be accommodated in the cavity of a package for transporting and/or storing nuclear fuel assemblies, and includes adjacent recesses. The device includes a plurality of transverse structures spaced apart by spacers, and sleeves each passing through an opening of at least one of the transverse structures, each sleeve being made from flat bars. In at least one transverse plane of the device passing through the sleeves, at least one of these sleeves has an inner recess-delimiting surface formed in part by: an inner surface of a first flat bar made with boron; and an inner surface of a second flat bar made without boron.

A storage device for transporting and/or storing nuclear fuel assemblies is intended to be accommodated in the cavity of a package for transporting and/or storing nuclear fuel assemblies, and includes adjacent recesses. The device includes a plurality of transverse structures spaced apart by spacers, and sleeves each passing through an opening of at least one of the transverse structures, each sleeve being made from flat bars. In at least one transverse plane of the device passing through the sleeves, at least one of these sleeves has an inner recess-delimiting surface formed in part by: an inner surface of a first flat bar made with boron; and an inner surface of a second flat bar made without boron.

A system and method of clearing radioactive contamination from a surface is provided by means of a handheld device and a method of using the handheld device. The handheld device has a manual system which operates by pressing a button to spray radioactive wash on the surface. The handheld device also has an electrical system which operates by pressing a button to suction radioactive contamination from the surface. The function of this system is to clean the surface from radioactive contamination. The system of the handheld device consists of a suctioning part and a pump and functions by suctioning the radioactive contamination into a lead cylinder, from which it is easily disposed. A third component includes a gauge for detecting contamination before, during, and after the cleaning and suctioning processes of the handheld device.

A system and method of clearing radioactive contamination from a surface is provided by means of a handheld device and a method of using the handheld device. The handheld device has a manual system which operates by pressing a button to spray radioactive wash on the surface. The handheld device also has an electrical system which operates by pressing a button to suction radioactive contamination from the surface. The function of this system is to clean the surface from radioactive contamination. The system of the handheld device consists of a suctioning part and a pump and functions by suctioning the radioactive contamination into a lead cylinder, from which it is easily disposed. A third component includes a gauge for detecting contamination before, during, and after the cleaning and suctioning processes of the handheld device.

A recovery tool for recovering a solid element, in particular a radioactive material. The recovery tool includes a chassis, a capture head and at least one cup. The capture head is movable with respect to the chassis between a retracted position and a deployed position. In the retracted position, the capture head is accommodated within a chamber of the recovery tool. In the deployed position, the capture head is able to capture the solid element. The cup is movable with respect to the chassis between an open position and a closed position. In the open position, the cup allows the capture head to be deployed. In the closed position of the cup, the cup allows the solid element to be retained within the chamber with the capture head in the retracted position.

A recovery tool for recovering a solid element, in particular a radioactive material. The recovery tool includes a chassis, a capture head and at least one cup. The capture head is movable with respect to the chassis between a retracted position and a deployed position. In the retracted position, the capture head is accommodated within a chamber of the recovery tool. In the deployed position, the capture head is able to capture the solid element. The cup is movable with respect to the chassis between an open position and a closed position. In the open position, the cup allows the capture head to be deployed. In the closed position of the cup, the cup allows the solid element to be retained within the chamber with the capture head in the retracted position.

A tamper-indicating assembly for a drum enclosure assembly is provided. The tamper-indicating assembly includes a tamper-indicating device that defines a cavity sized to receive and surround at least a portion of the closure bolt, the first flanged end, and the second flanged end to prevent movement of the closure bolt. A tab extends radially outward from the tamper-indicating device with respect to an axial centerline of the tamper-indicating assembly. The tamper-indicating assembly further includes a pin non-removably coupled to the tamper-indicating device. The pin extends through the tamper-indicating device and across the cavity such that the tamper-indicating device and the pin collectively surround the closure bolt. The exemplary tamper-indicating device described herein includes features that facilitate the robotic application of the tamper-indicating device to a drum enclosure.

A nuclear component handling arrangement is disclosed including a storage overpack including an inner envelope, an inner canister including an outer envelope, and a vent and duct system. The inner canister is positionable within the storage overpack. The vent and duct system includes an inlet vent, an outlet vent, and a passageway defined between the inner envelope of the storage overpack and the outer envelope of the inner canister. The passageway extends between the inlet vent and the outlet vent. The inlet vent includes an inlet entrance, an inlet exit, and a curved transition surface extending between the inlet entrance and the inlet exit.

A chargeable atomic battery (CAB) and a standardized pre-irradiation encapsulation manufacturing method. A CAB unit is manufactured through a non-radioactive process and then placed in a radiation field (typically a fission reactor) to convert a portion of a non-radioactive precursor material into an activated material (e.g., radioisotope) for charging. After charging, the CAB unit is ready for use and can be combined with additional CAB units into a CAB stack to achieve the desired activity and then integrated into a CAB pack or a product that uses the radioactivity for the desired application such as heating, electricity, and passive x-ray sources. The pre-irradiation encapsulation manufacturing method uses a die press and sintering process to produce the CAB unit with the precursor material fully encapsulated by the encapsulation material. During and after the charging process, the encapsulation material serves as a barrier, preventing release of the activated material release.