Patent classifications
G21F5/012
NUCLEAR WASTE CASK WITH IMPACT PROTECTION, IMPACT AMELIORATION SYSTEM FOR NUCLEAR FUEL STORAGE, UNVENTILATED CASK FOR STORING NUCLEAR WASTE, AND STORAGE AND TRANSPORT CASK FOR NUCLEAR WASTE
A nuclear waste cask with impact protection includes impact limiters comprising deformable energy-absorbing perforated sleeves. An impact amelioration system for nuclear fuel storage components includes impact limiter assemblies at the bottom cask to canister interface including impact limiter plugs frictionally engaging corresponding plug holes formed in the cask closure plate. A nuclear waste fuel storage system includes an unventilated cask including a heavy free-floating radiation shielding lid loosely coupled the top end of the cask in a movable manner via the anchor bosses which provides cask overpressurization protection. A nuclear waste cask includes an axially elongated rectangular cuboid cask body having a cavity for holding nuclear waste materials and cask locking mechanism including first locking protrusions on the lid which are selectively interlockable with mating second locking protrusions on the cask body to lock the lid to the cask body.
NUCLEAR WASTE CASK WITH IMPACT PROTECTION, IMPACT AMELIORATION SYSTEM FOR NUCLEAR FUEL STORAGE, UNVENTILATED CASK FOR STORING NUCLEAR WASTE, AND STORAGE AND TRANSPORT CASK FOR NUCLEAR WASTE
A nuclear waste cask with impact protection includes impact limiters comprising deformable energy-absorbing perforated sleeves. An impact amelioration system for nuclear fuel storage components includes impact limiter assemblies at the bottom cask to canister interface including impact limiter plugs frictionally engaging corresponding plug holes formed in the cask closure plate. A nuclear waste fuel storage system includes an unventilated cask including a heavy free-floating radiation shielding lid loosely coupled the top end of the cask in a movable manner via the anchor bosses which provides cask overpressurization protection. A nuclear waste cask includes an axially elongated rectangular cuboid cask body having a cavity for holding nuclear waste materials and cask locking mechanism including first locking protrusions on the lid which are selectively interlockable with mating second locking protrusions on the cask body to lock the lid to the cask body.
Nuclear materials apparatus and implementing the same
An apparatus for supporting spent nuclear fuel including a plurality of wall plates arranged in an intersecting manner to define a basket apparatus extending along a longitudinal axis. The basket apparatus may include a plurality of fuel cells and a plurality of flux traps between adjacent fuel cells. A plurality of reinforcement members may be positioned in the flux traps and may extend between opposing ones of the wall plates that form the flux traps. Each of the wall plates may be a slotted wall plate. The slotted wall plates may be interlocked with one another to form the basket apparatus. Each of the slotted wall plates may include an upper edge, a lower edge, and a plurality of plate slots formed in each of the upper and lower edges. The plate slots of the slotted wall plates may receive intersecting slotted wall plates.
Storage basket for radioactive materials, having an optimised space requirement and housings with more accurate geometry
A storage basket for radioactive materials, defining housings parallel to each other and each extending along a housing axis parallel to a longitudinal central axis of the basket, the latter including: a plurality of transverse plates, traversed by a plurality of openings; a plurality of housing tubes arranged parallel to the longitudinal central axis of the basket. The housing tubes are arranged in alternation with the transverse plates along the axis, such that the inner lateral surface of each housing is defined, successively along this axis, at least by the inner surface of a first housing tube, the inner surface of one of the openings of a first transverse plate, and the inner surface of a second housing tube.
Storage basket for radioactive materials, having an optimised space requirement and housings with more accurate geometry
A storage basket for radioactive materials, defining housings parallel to each other and each extending along a housing axis parallel to a longitudinal central axis of the basket, the latter including: a plurality of transverse plates, traversed by a plurality of openings; a plurality of housing tubes arranged parallel to the longitudinal central axis of the basket. The housing tubes are arranged in alternation with the transverse plates along the axis, such that the inner lateral surface of each housing is defined, successively along this axis, at least by the inner surface of a first housing tube, the inner surface of one of the openings of a first transverse plate, and the inner surface of a second housing tube.
Passive cooling device for casks containing nuclear fuel
A system for externally cooling a cask containing heat-emitting spent nuclear fuel includes the cask comprising a radiation shielding body defining an internal cavity configured to hold a canister containing the spent nuclear fuel. A continuously annular cooling jacket extends circumferentially around an external surface of the cask body. The cooling jacket may have a double shell construction including an internal cavity for a cooling medium which provides an external heat sink for absorbing heat radiated from the external wall surface of the cask generated by the spent nuclear fuel. The heat emitted by the spent nuclear fuel is absorbed by the cooling medium in the cooling jacket, thereby in turn cooling the cask. In one embodiment, the cooling medium may be dry ice which undergoes sublimation by absorbing the heat to change from solid to gaseous phase directly. The jacket may be formed of multiple segments.
Passive cooling device for casks containing nuclear fuel
A system for externally cooling a cask containing heat-emitting spent nuclear fuel includes the cask comprising a radiation shielding body defining an internal cavity configured to hold a canister containing the spent nuclear fuel. A continuously annular cooling jacket extends circumferentially around an external surface of the cask body. The cooling jacket may have a double shell construction including an internal cavity for a cooling medium which provides an external heat sink for absorbing heat radiated from the external wall surface of the cask generated by the spent nuclear fuel. The heat emitted by the spent nuclear fuel is absorbed by the cooling medium in the cooling jacket, thereby in turn cooling the cask. In one embodiment, the cooling medium may be dry ice which undergoes sublimation by absorbing the heat to change from solid to gaseous phase directly. The jacket may be formed of multiple segments.
CANISTER APPARATUS AND/OR FUEL RACK FOR STORING AND/OR TRANSPORTING SPENT NUCLEAR FUEL
An apparatus for supporting radioactive fuel assemblies, such as spent nuclear fuel. In one aspect, the apparatus is in the form of a fuel rack having adjustable height pedestals. In another aspect, the apparatus is a canister including a first pressure vessel forming a first cavity and a second pressure vessel forming a second cavity, the first pressure vessel located in the second cavity of the second pressure vessel. An inner surface of the second pressure vessel may be in continuous surface contact with an outer surface of the first pressure vessel to form a dual-walled canister.
CANISTER APPARATUS AND/OR FUEL RACK FOR STORING AND/OR TRANSPORTING SPENT NUCLEAR FUEL
An apparatus for supporting radioactive fuel assemblies, such as spent nuclear fuel. In one aspect, the apparatus is in the form of a fuel rack having adjustable height pedestals. In another aspect, the apparatus is a canister including a first pressure vessel forming a first cavity and a second pressure vessel forming a second cavity, the first pressure vessel located in the second cavity of the second pressure vessel. An inner surface of the second pressure vessel may be in continuous surface contact with an outer surface of the first pressure vessel to form a dual-walled canister.
Storage system for radioactive nuclear waste with pressure surge protection
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.