A radioactive nuclear waste storage system includes a cask comprising a hermetically sealed internal cavity configured for holding the waste such as spent nuclear fuel submerged in an inventory of water. One or more pressure surge capacitors disposed inside the cask include a vacuum cavity evacuated to sub-atmospheric conditions prior to storage of fuel in the cask. At least one rupture disk seals a vacuum chamber inside each capacitor. Each rupture disk is designed and constructed to burst at a predetermined burst pressure level occurring inside the cask external to the capacitor. This allows excess cask pressure occurring during a high pressure excursion resulting from abnormal operating conditions to bleed into capacitor, thereby returning the pressure inside the cask to acceptable levels. In one embodiment, the capacitors are located in peripheral regions of the cask cavity adjacent to the circumferential wall of the cask body.

An example radiographic source exposure device includes: a housing; a radiographic source capsule within the housing, the radiographic source capsule having a radionuclide; a shield within the housing and configured to shield the radiographic source capsule and to permit extension of the radiographic source capsule to expose the radiographic source capsule; one or more sensors coupled to the housing, the one or more sensors configured to detect sensor data comprising one or more of: a count of exposure cycles, a length between the radiographic source capsule position and a stored position, a surface dose, a source decay of the radiographic source, a locking device locking mode status, an unlocking key status, a radiographic source exposure device orientation, a particulate count within the shield, a shock event, or shield wear; a processing system within the housing and configured to store the sensor data and output the sensor data; and a power source within the housing and configured to provide power to the processing system.

An example radiographic source exposure device includes: a housing; a radiographic source capsule within the housing, the radiographic source capsule having a radionuclide; a shield within the housing and configured to shield the radiographic source capsule and to permit extension of the radiographic source capsule to expose the radiographic source capsule; one or more sensors coupled to the housing, the one or more sensors configured to detect sensor data comprising one or more of: a count of exposure cycles, a length between the radiographic source capsule position and a stored position, a surface dose, a source decay of the radiographic source, a locking device locking mode status, an unlocking key status, a radiographic source exposure device orientation, a particulate count within the shield, a shock event, or shield wear; a processing system within the housing and configured to store the sensor data and output the sensor data; and a power source within the housing and configured to provide power to the processing system.

A container holds radioactive material. A sub-criticality controller protects the radioactive material from reaching a criticality from contact with the water. The sub-criticality controller includes a metallic composition having at least one metal component and at least one borate component bonded to the at least one metal component. The metallic composition forms borates from the borate component when the metallic composition contacts the water.

A method of drying transport and/or storage containers for radioactive waste has the first step draining or pumping residual water out of the container holding the nuclear waste. Then gas is evacuated from the interior of the drained or pumped out container interior. Thereafter an inert gas is fed into the drained or pumped out container interior while continuing to evacuate gas from the container interior. During the evacuation and/or infeeding of inert gas a rate of evacuation and/or a rate of infeed of the inert gas is controlled such such that an inert-gas content in the interior of the container is between 50 and 95 vol %.

A method of drying transport and/or storage containers for radioactive waste has the first step draining or pumping residual water out of the container holding the nuclear waste. Then gas is evacuated from the interior of the drained or pumped out container interior. Thereafter an inert gas is fed into the drained or pumped out container interior while continuing to evacuate gas from the container interior. During the evacuation and/or infeeding of inert gas a rate of evacuation and/or a rate of infeed of the inert gas is controlled such such that an inert-gas content in the interior of the container is between 50 and 95 vol %.

A package for transporting and/or storing radioactive materials, comprises a cavity for housing radioactive materials, as well as a radiological protection device comprising radiological protection elements arranged in an annular space, at least two successive radiological protection elements along a given direction of the annular space, from a longitudinal direction and a circumferential direction, and a locking member designed to limit and/or prevent the distancing of the two radiological protection elements relative to one another in a given direction.

A radiation shield assembly is described, configured to block radiation emanating from a radiation source from reaching a user. Two shields are supported by a support arm, and are configured to rotate and translate relative to one another about the support arm's longitudinal axis. This allows the shield to be easily configured and reconfigured as necessary to visualize various parts of a patient's body via radiography. The assembly is articulated to overcome difficulties in maneuvering it around an operating room. Such articulation may come in the form of a dual-sleeve configuration for jointing the shield, in the form of adjustable wheels on the floor sand, or both.

A radiation shield assembly is described, configured to block radiation emanating from a radiation source from reaching a user. Two shields are supported by a support arm, and are configured to rotate and translate relative to one another about the support arm's longitudinal axis. This allows the shield to be easily configured and reconfigured as necessary to visualize various parts of a patient's body via radiography. The assembly is articulated to overcome difficulties in maneuvering it around an operating room. Such articulation may come in the form of a dual-sleeve configuration for jointing the shield, in the form of adjustable wheels on the floor sand, or both.

A passive venting arrangement for use in venting of gases produced by radioactive materials includes a source gas region for receiving the gases produced by the radioactive materials; a filter ullage region disposed above the source gas region and segregated therefrom except for a plurality of bore holes which each extend between, and fluidly couple, the source gas region and the filter ullage region; and a plurality of filters disposed in contact with the filter ullage region, wherein each filter is structured to provide for the exchange of gases from the filter ullage region through the filter to an ambient environment.