A method of improving residual stress in a canister in which fuel assemblies are loaded includes, when the canister having a cylindrical canister shell and a canister lid welded to the upper opening of the canister shell is disposed in a cylindrical cask body, filling the space above and around an upper end portion of the canister in the cask body with fill water. Then, compressive stress is applied to a predetermined region of the upper end portion of the canister in the fill water. This makes it possible to readily apply compressive stress to the canister while shielding radioactive rays by the fill water.

The present invention provides a dry interim storage container for spent nuclear fuel, precisely a dry interim storage container that can be filled with spent nuclear fuel wherein the storage container space is also filled with metal particles. The dry storage container for spent nuclear fuel of the present invention is filled with particles in its empty space for the spent nuclear fuel, which is advantageous in cooling efficiency and maintenance cost, compared with the conventional storage method using gas.

A system for the storage of a radioactive waste product, wherein the radioactive waste product is located in a container and where one or more containers are stored in a bore hole drilled beneath a surface and having a bottom, wherein following placement of the one or more containers in the bore hole closer to the bottom, a fluid is added to the bore hole to a height above the upper most container, and wherein an upper cover is located above the upper most container and above the fluid to seal in the one or more containers and a non-permeable material is placed above the upper cover, a container storage area being formed within the bore hole beneath the upper cover.

Disclosed herein are systems and methods for a modular reconfigurable shielding system for one or more storage containers in temporary or long term storage. The system comprises shield panels which may be used to shield external faces of containers in a storage configuration to reduce the overall amount of shielding required in a storage facility. Reducing the amount of shielding reduces the storage footprint of each container thus increasing storage capacity and efficiency of the storage facility. The modularity of the shield panels allows storage containers to be easily added and removed from the storage configuration. Additionally, modular shielding allows the amount and type of shielding to be easily reconfigured for differing requirements and storage contents.

Disclosed herein are systems and methods for a modular reconfigurable shielding system for one or more storage containers in temporary or long term storage. The system comprises shield panels which may be used to shield external faces of containers in a storage configuration to reduce the overall amount of shielding required in a storage facility. Reducing the amount of shielding reduces the storage footprint of each container thus increasing storage capacity and efficiency of the storage facility. The modularity of the shield panels allows storage containers to be easily added and removed from the storage configuration. Additionally, modular shielding allows the amount and type of shielding to be easily reconfigured for differing requirements and storage contents.

A storage apparatus is provided for dry storage of radioactive nuclear waste. The storage apparatus comprises a sealed canister containing the radioactive nuclear waste and an outer ventilated metal storage overpack (VMSO). The VMSO has a plurality of vents to enable ambient air flow through the VMSO and around the canister to thereby dissipate heat from the canister. The VMSO has a side wall having an inner metal layer and one or more sets of alternating layers. Each set includes a neutron absorbing layer adjacent to another metal layer so that neutron absorbing and metal layers alternate throughout the side wall. The neutron absorbing layer or layers are designed to absorb neutron particles radiated from the radioactive nuclear waste and the metal layers are designed to absorb gamma particles radiated from the radioactive nuclear waste as well as radiated from the neutron absorbing layer or layers that result from reactions associated with absorption of neutron particles.

A storage apparatus is provided for dry storage of radioactive nuclear waste. The storage apparatus comprises a sealed canister containing the radioactive nuclear waste and an outer ventilated metal storage overpack (VMSO). The VMSO has a plurality of vents to enable ambient air flow through the VMSO and around the canister to thereby dissipate heat from the canister. The VMSO has a side wall having an inner metal layer and one or more sets of alternating layers. Each set includes a neutron absorbing layer adjacent to another metal layer so that neutron absorbing and metal layers alternate throughout the side wall. The neutron absorbing layer or layers are designed to absorb neutron particles radiated from the radioactive nuclear waste and the metal layers are designed to absorb gamma particles radiated from the radioactive nuclear waste as well as radiated from the neutron absorbing layer or layers that result from reactions associated with absorption of neutron particles.

Steel and/or copper spherical capsules are specifically engineered and manufactured for housing uranium waste products. The uranium waste products are placed within the spherical capsules. Human-made cavern(s) and/or substantially lateral wellbore(s) are constructed for receiving the uranium waste containing spherical capsules. The human-made cavern(s) and/or the substantially lateral wellbore(s) are deeply located in specific types of geologic rock formations thousands of feet below the Earth's surface. These uranium waste containing spherical capsules are loaded from the Earth's surface into the human-made cavern(s) and/or into the substantially lateral wellbore(s). The emplaced spherical capsules are surrounded by an immersive protective medium within the given human-made cavern(s) and/or within the substantially lateral wellbore(s). The given human-made cavern(s) and/or the given substantially lateral wellbore(s), with the uranium waste containing spherical capsules, are sealed off.

Steel and/or copper spherical capsules are specifically engineered and manufactured for housing uranium waste products. The uranium waste products are placed within the spherical capsules. Human-made cavern(s) and/or substantially lateral wellbore(s) are constructed for receiving the uranium waste containing spherical capsules. The human-made cavern(s) and/or the substantially lateral wellbore(s) are deeply located in specific types of geologic rock formations thousands of feet below the Earth's surface. These uranium waste containing spherical capsules are loaded from the Earth's surface into the human-made cavern(s) and/or into the substantially lateral wellbore(s). The emplaced spherical capsules are surrounded by an immersive protective medium within the given human-made cavern(s) and/or within the substantially lateral wellbore(s). The given human-made cavern(s) and/or the given substantially lateral wellbore(s), with the uranium waste containing spherical capsules, are sealed off.

The present invention relates to a constructing method for delaying corrosion of radioactive waste disposal container in concrete disposal vault and, more specifically, to a constructing method for delaying corrosion of radioactive waste disposal container in concrete disposal vault in which backfill, placed to the top, combines pH control capsules, thereby dissolving the pH control capsules in rainwater, and a pH controller, inside, is discharged, thereby preventing decrease of pH of the backfill below 8.5 and delaying corrosion in the disposal containers, upon filling in backfill after placing radioactive waste disposal containers in the concrete vault.