Systems and methods of transferring nuclear fuel from fuel pools having size and/or weight limitations to a storage or transport cask are disclosed. A canister containing spent nuclear fuel is inserted into a transfer cask. A shielding sleeve is then placed around the transfer cask. A lifting device simultaneously lifts the transfer cask and the shielding sleeve over a storage cask and the spent fuel is transferred from the transfer cask to the storage or transport cask.

Systems and methods of transferring nuclear fuel from fuel pools having size and/or weight limitations to a storage or transport cask are disclosed. A canister containing spent nuclear fuel is inserted into a transfer cask. A shielding sleeve is then placed around the transfer cask. A lifting device simultaneously lifts the transfer cask and the shielding sleeve over a storage cask and the spent fuel is transferred from the transfer cask to the storage or transport cask.

A transport or storage container holding radioactive waste and a body of water is dried by the steps of first draining or pumping out the body of water and thereby leaving residual water in the container. Then at least one solid drying agent is introduced into an interior the container for removing from the interior of the container for removing the physically or chemically bonded residual water. The solid drying agent is an alkaline earth salt, particularly an alkaline earth oxide.

A transport or storage container holding radioactive waste and a body of water is dried by the steps of first draining or pumping out the body of water and thereby leaving residual water in the container. Then at least one solid drying agent is introduced into an interior the container for removing from the interior of the container for removing the physically or chemically bonded residual water. The solid drying agent is an alkaline earth salt, particularly an alkaline earth oxide.

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 when the metallic composition contacts the water.

Self-loading systems and methods for disposal of waste materials in a deep underground formation may include at least one wellbore that runs from the Earth's surface to the deep underground formations, wellbore viscous fluid within that at least one wellbore, and at least one waste capsule, wherein the at least one waste capsules houses some waste and is configured to fall within both the at least one wellbore and the wellbore viscous fluid. The systems and methods may also include at least one human-made cavern located in the deep underground formation and connected to the at least one wellbore, wherein the at least one human-made cavern may be configured to receive the at least one waste capsule. The systems and methods may also include a counter for counting waste capsules and/or a robot for dropping waste capsules into a wellhead leading to the at least one wellbore.

Provided is a standard for mobile equipment for measuring structural deformation of a nuclear fuel assembly, the standard including: a fixed frame fixed to one side of measuring equipment accommodated in a container; a standard member configured to be attached to and detached from the fixed frame, to rotate with one end portion of the fixed frame as a center, and to correspond to a nuclear fuel assembly standard specification, wherein an upper plate provided with a coupling means configured to be coupled with a transport device is coupled on one end portion of the standard member, a lower plate configured to be erected upright on and fixed to one side of the measuring equipment is coupled on an opposite end portion of the standard member.

A safety vial system has a vial adapter subsystem irreversibly mountable to the top of a vial containing a hazardous medicament and a vial base subsystem sealingly engaging a lower portion of the vial adapter subsystem and telescopically movable therein from a first position providing a path for gas sterilization around the vial to a second position wherein the path is closed to form a sterilized expandable, neutral pressure bellows chamber around and below the vial. The device has a removable top cap, a pierceable barrier film, a normally closed needleless valve in fluid communication with a dual lumen spike initially disposed above the film and a frangible product integrity ring holding the activation housing in place for sealed telescopic movement on a main body that surrounds the vial. The user pulls the product integrity ring and removes it, and then pushes the activation housing axially downward until it clicks to lock the device in the activated position wherein both lumens of the spike are in communication with the inside of the vial. The user removes the top cap on the activation housing assembly, and then uses a needleless syringe with an adapter thereon to add diluent and mixes if needed and withdraw drug from the vial via the valve.

Basket for a transportation and storage cask for spent nuclear fuel from a pressurized water reactor, containing a base on which steel disks are fixed in height and aluminum disks are located between the steel disks equidistantly. Vertical clamping elements connect the steel and aluminum disks into a section cover. Two rows of apertures are made in the disks relative to their axis, two aperture in the inner row and eight in the outer row. The apertures comprise channels. Vertical clamping elements are located along the outer perimeter of the disks. The basket is made of one section and equipped with additional vertical disk clamping elements located in a circle between axes of the inner and outer rows of apertures in the disks The apertures and channels are round so that canisters for spent fuel assemblies can be placed therin. Grooves and hooks for canisters are provided in the base.

Basket for a transportation and storage cask for spent nuclear fuel from a pressurized water reactor, containing a base on which steel disks are fixed in height and aluminum disks are located between the steel disks equidistantly. Vertical clamping elements connect the steel and aluminum disks into a section cover. Two rows of apertures are made in the disks relative to their axis, two aperture in the inner row and eight in the outer row. The apertures comprise channels. Vertical clamping elements are located along the outer perimeter of the disks. The basket is made of one section and equipped with additional vertical disk clamping elements located in a circle between axes of the inner and outer rows of apertures in the disks The apertures and channels are round so that canisters for spent fuel assemblies can be placed therin. Grooves and hooks for canisters are provided in the base.