Abstract: A nuclear component handling arrangement is disclosed including a storage overpack including an inner envelope, an inner canister including an outer envelope, and a vent and duct system. The inner canister is positionable within the storage overpack. The vent and duct system includes an inlet vent, an outlet vent, and a passageway defined between the inner envelope of the storage overpack and the outer envelope of the inner canister. The passageway extends between the inlet vent and the outlet vent. The inlet vent includes an inlet entrance, an inlet exit, and a curved transition surface extending between the inlet entrance and the inlet exit.

Abstract: A modular dry spent fuel canister system in which several different types of inner spent nuclear fuel canisters can be loaded into the same outer cask family. This family typically includes a storage overpack, a transfer cask, a transportation cask and support or auxiliary hardware. The various canisters can be loaded interchangeably into the different types of outer casks. The inner canisters are differentiated not by physical fuel type or dimension, but by the engineering objective or criterion that applies to the spent fuel being stored. One such objective may be for a single canister to store a large number of assemblies economically and safely. A second is a canister designed to greatly reduce the cooling time (or radioactive decay time) that must pass in order to load spent nuclear fuel for off-site storage, so as to meet the decay heat requirements and capabilities of the off-site storage system.

Abstract: A modular dry spent fuel canister system in which several different types of inner spent nuclear fuel canisters can be loaded into the same outer cask family. This family typically includes a storage overpack, a transfer cask, a transportation cask and support or auxiliary hardware. The various canisters can be loaded interchangeably into the different types of outer casks. The inner canisters are differentiated not by physical fuel type or dimension, but by the engineering objective or criterion that applies to the spent fuel being stored. One such objective may be for a single canister to store a large number of assemblies economically and safely. A second is a canister designed to greatly reduce the cooling time (or radioactive decay time) that must pass in order to load spent nuclear fuel for off-site storage, so as to meet the decay heat requirements and capabilities of the off-site storage system.

Abstract: The invention relates to a thermal conduction element (20) for a package for transporting and/or storing radioactive materials, comprising: an internal part (30) intended to be in contact with a lateral body (14) of the package; an external part (34) intended to form a portion of an external envelope (24) of said package, holding radiological protection means (22); an intermediate part (32) arranged between the internal and external parts, the internal, external and intermediate parts being produced from copper and one of the alloys thereof. According to the invention, the external part (34) is equipped, at each of its two opposite ends, with an area (36) for connection by welding to another thermal conduction element (20), each connection area (36) being produced from steel.

Abstract: The invention relates to a thermal conduction element (20) for a package for transporting and/or storing radioactive materials, comprising: an internal part (30) intended to be in contact with a lateral body (14) of the package; an external part (34) intended to form a portion of an external envelope (24) of said package, holding radiological protection means (22); an intermediate part (32) arranged between the internal and external parts, the internal, external and intermediate parts being produced from copper and one of the alloys thereof. According to the invention, the external part (34) is equipped, at each of its two opposite ends, with an area (36) for connection by welding to another thermal conduction element (20), each connection area (36) being produced from steel.

Abstract: A method of manufacturing a porous ceramic part, comprising the following steps in succession: a) preparing a mixture M containing a ceramic powder in suspension, at least one gelling agent and at least one foaming agent, at a mixing temperature which is higher than the gelling temperature of the gelling agent; b) shearing the mixture M at a foaming temperature which is higher than the gelling temperature, to obtain a foam; c) gelling the foam by cooling the mixture M to a temperature below the gelling temperature of the gelling agent; and d) drying the gelled foam to obtain a perform. According to the invention, a stabilizing agent is added to the mixture M, which agent has an instantaneous viscosity, in Pa·s, that increases by a factor of at least ten when a shear rate of the stabilizing agent is reduced from 100 s?1 to 0.

Abstract: A method of manufacturing a porous ceramic part, comprising the following steps in succession: a) preparing a mixture M containing a ceramic powder in suspension, at least one gelling agent and at least one foaming agent, at a mixing temperature which is higher than the gelling temperature of the gelling agent; b) shearing the mixture M at a foaming temperature which is higher than the gelling temperature, to obtain a foam; c) gelling the foam by cooling the mixture M to a temperature below the gelling temperature of the gelling agent; and d) drying the gelled foam to obtain a perform. According to the invention, a stabilizing agent is added to the mixture M, which agent has an instantaneous viscosity, in Pa·s, that increases by a factor of at least ten when a shear rate of the stabilizing agent is reduced from 100 s?1 to 0.