A container for storing and/or transporting spent nuclear fuel. The container includes a body that defines an internal cavity that holds the spent nuclear fuel and an outer surface. The outer surface has holes formed therein into which trunnions are positioned. The container can be lifted by a lift yoke by coupling the lift yoke to the trunnions. The trunnions may include first and second components such that the first component is slidable in its axial direction relative to the second component when a force that exceeds a threshold acts on the second component. Thus, the second component may be slidable between a protruded state in which a portion of the second component protrudes from the outer surface of the body and a retracted state in which the second component does not protrude from the outer surface of the body.

An underground ventilated system for storing nuclear waste materials. The system includes a storage module having an outer shell defining an internal cavity and an inner shell. A majority of the height of the outer shell may be disposed below grade. The outer shell may include a hermetically sealed bottom. First and second canisters are positioned in lower and upper portions within the cavity respectively in vertically stacked relationship. A centering and spacing ring assembly is interspersed between the first and second canisters to transfer the weight of the upper second canister to the lower first canister. The assembly may include centering lugs which laterally restrain the first and second canisters in case of a seismic event. A natural convection driven ventilated air system cools the canisters to remove residual decay heat to the atmosphere. In one non-limiting embodiment, the shells are made of steel.

The present disclosure relates to a transfer cask for transferring spent nuclear fuel. The transfer cask transfers a canister storing the spent nuclear fuel and includes a transfer container having a space for accommodating the canister; a neutron shielding body arranged on an outer periphery of the transfer container to shield neutrons; and an opening/closing portion that is coupled to a lower portion of the transfer container and opens and closes the lower portion of the transfer container, wherein the opening and closing portion, a support portion supporting the transfer container and having a first through hole in communication with the transfer container; a lid assembly having a first lid portion and a second lid portion that open and close the first through hole; and a base plate on which the support portion is seated and a second through hole through which the canister is drawn out is formed.

An apparatus for analyzing nuclides and the concentration thereof in waste contained in a radioactive waste packaging container according to the present disclosure relates to an apparatus that has detector devices located above/under the waste packaging container and performs nuclide and concentration analysis on the waste in the packaging container by scanning the packaging container in the longitudinal direction thereof using a forward/backward driving device. In particular, upper/lower detector modules are equipped with multiple high-resolution gamma ray detectors to increase inspection efficiency, each module is designed to be driven up/down, and each detector in the module is designed to be driven left/right, thereby performing nuclide and concentration analysis on various types of packaging containers regardless of the size thereof.

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 a 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.

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 a 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 nuclear waste storage system includes a human-unoccupiable directional drillhole formed from a terranean surface into a subterranean formation, the drillhole including a substantially vertical portion and a substantially horizontal portion that includes a hazardous waste repository for nuclear waste storage; a casing including one or more tubular sections sized to fit within the drillhole; and a coating attached to an exterior surface of the casing, the exterior surface facing a rock formation through which the drillhole is formed.

A nuclear waste storage system includes a human-unoccupiable directional drillhole formed from a terranean surface into a subterranean formation, the drillhole including a substantially vertical portion and a substantially horizontal portion that includes a hazardous waste repository for nuclear waste storage; a casing including one or more tubular sections sized to fit within the drillhole; and a coating attached to an exterior surface of the casing, the exterior surface facing a rock formation through which the drillhole is formed.

The present invention is directed to new and improved industrial containment bags wherein the improvement comprises providing methods and technologies for improving the integrity of such bags during processes designed for lifting, transporting storing and/or disposing of the same. In certain embodiments, the improvement includes providing methods and technologies for improving the sealing capabilities of the bag's closure systems. In other embodiments, the improvement includes providing methods and technologies for assessing the load balance of materials being contained in such industrial containment bags; and thereafter, compensating for any significant load imbalances. The present invention is also directed to methods of manufacturing, using, filling, lifting, transporting, storing, and/or disposing of such new and improved industrial containment bags.

The present invention is directed to new and improved industrial containment bags wherein the improvement comprises providing methods and technologies for improving the integrity of such bags during processes designed for lifting, transporting storing and/or disposing of the same. In certain embodiments, the improvement includes providing methods and technologies for improving the sealing capabilities of the bag's closure systems. In other embodiments, the improvement includes providing methods and technologies for assessing the load balance of materials being contained in such industrial containment bags; and thereafter, compensating for any significant load imbalances. The present invention is also directed to methods of manufacturing, using, filling, lifting, transporting, storing, and/or disposing of such new and improved industrial containment bags.