A system and method for drying cavities containing spent nuclear fuel is devised. The invention utilizes a non-intrusive procedure that is based on monitoring the dew point temperature of a non-reactive gas that is circulated through the cavity. In one aspect, the invention is a system for drying a cavity loaded with spent nuclear fuel comprising: a canister forming the cavity, the cavity having an inlet and an outlet; a source of non-reactive gas; means for flowing the non-reactive gas from the source of non-reactive gas through the cavity; and means for repetitively measuring the dew point temperature of the non-reactive gas exiting the cavity.

A container for holding radioactive waste has a side wall, a floor connected to a lower end of the side wall, and a cover. A set of side-wall formations is provided at an upper end of the side wall and on an inner surface of the side wall, and a set of cover-edge formations is distributed around an outer edge of the cover and fittable with the side-wall formations. Thus, as a result of the interfitting of cover-edge formations with the side-wall formations, the cover can be or is fixedly connected to the side wall without welds.

A container for holding radioactive waste has a side wall, a floor connected to a lower end of the side wall, and a cover. A set of side-wall formations is provided at an upper end of the side wall and on an inner surface of the side wall, and a set of cover-edge formations is distributed around an outer edge of the cover and fittable with the side-wall formations. Thus, as a result of the interfitting of cover-edge formations with the side-wall formations, the cover can be or is fixedly connected to the side wall without welds.

The present disclosure relates to a sliding type transfer cask for transferring spent nuclear fuel. The sliding type transfer cask includes a transfer container having a space for accommodating a canister; a neutron shielding body disposed around an outer circumference; and an opening/closing portion coupled to a lower portion of the transfer container. The opening/closing portion includes a support portion that has a first through-hole communicating with the transfer container and supports the transfer container; a base plate that is arranged below the support portion; and a lid assembly that includes a first lid portion and a second lid portion. The first lid portion includes a first lid and a first motor for sliding the first lid. The second lid portion includes a second lid and a second motor for sliding the second lid.

The present disclosure relates to a sliding type transfer cask for transferring spent nuclear fuel. The sliding type transfer cask includes a transfer container having a space for accommodating a canister; a neutron shielding body disposed around an outer circumference; and an opening/closing portion coupled to a lower portion of the transfer container. The opening/closing portion includes a support portion that has a first through-hole communicating with the transfer container and supports the transfer container; a base plate that is arranged below the support portion; and a lid assembly that includes a first lid portion and a second lid portion. The first lid portion includes a first lid and a first motor for sliding the first lid. The second lid portion includes a second lid and a second motor for sliding the second lid.

Apparatus and method for drying spent nuclear fuel loaded in a cavity of a canister. A non-reactive gas discharged from the canister is selectively circulated through one of a contaminated circulation system and a non-contaminated circulation system according to a measured radiation dose rate.

Apparatus and method for drying spent nuclear fuel loaded in a cavity of a canister. A non-reactive gas discharged from the canister is selectively circulated through one of a contaminated circulation system and a non-contaminated circulation system according to a measured radiation dose rate.

The present invention relates to a disposal container and a storage system for high-level radioactive waste and, more specifically, to a disposal container for high-level radioactive waste using multiple barriers and a barrier system using thereof, the disposal container having the multiple barriers consisting of an inner wall made of carbon steel for excellent corrosion resistance and ease of manufacture, a middle wall made of Inconel, which is bonded to a lateral surface of the inner wall, and an outer wall made of copper, which is bonded to a lateral surface of the middle wall.

A method for preventing corrosion of a spent nuclear fuel canister by using electrolytic corrosion protection, according to the present invention, has an effect of enabling a semi-permanent operation and, particularly, has effects of preventing oxidation and corrosion problems of a canister made of a metal material, in consideration of various environmental variables that may cause corrosion, and ensuring the structural stability of the canister so as to enable a semi-permanent operation.

A method for preventing corrosion of a spent nuclear fuel canister by using electrolytic corrosion protection, according to the present invention, has an effect of enabling a semi-permanent operation and, particularly, has effects of preventing oxidation and corrosion problems of a canister made of a metal material, in consideration of various environmental variables that may cause corrosion, and ensuring the structural stability of the canister so as to enable a semi-permanent operation.