Abstract: The present invention provides a cask (10) for transport and short-term storage of spent nuclear fuel. The cask 10 includes a structural shell (14) defining a cavity (40) for receiving spent nuclear fuel. The shell is formed from an upper shell portion (16) formed of a first metal and a lower shell portion (18) formed from a second metal. The first metal utilized to form the upper shell portion has a higher load bearing strength than the second metal utilized to form the lower shell portion. A bearing surface is defined on the upper shell portion by trunnions (30) mounted within sleeves (32) secured to the upper shell portion. The trunnions (30) each define a bearing projection (160) that is engageable to enable hoisting of the cask, with the tensile and shear loads of hoisting the cask being transferred from the trunnions to the trunnion mounting sleeves, and thus to the upper shell portion of the structural shell.

Abstract: The present invention provides a cask (10) for transport and short-term storage of spent nuclear fuel. The cask 10 includes a structural shell (14) defining a cavity (40) for receiving spent nuclear fuel. The shell is formed from an upper shell portion (16) formed of a first metal and a lower shell portion (18) formed from a second metal. The first metal utilized to form the upper shell portion has a higher load bearing strength than the second metal utilized to form the lower shell portion. A bearing surface is defined on the upper shell portion by trunnions (30) mounted within sleeves (32) secured to the upper shell portion. The trunnions (30) each define a bearing projection (160) that is engageable to enable hoisting of the cask, with the tensile and shear loads of hoisting the cask being transferred from the trunnions to the trunnion mounting sleeves, and thus to the upper shell portion of the structural shell.

Abstract: A skid for transporting a nuclear fuel transportation cask. The skid comprises a supporting member having parallel spaced-apart plates. The plates are aligned perpendicular to a longitudinal axis of the cask, include a semi-circular trough for mating with the cask, and are connected by longitudinal fins parallel to the longitudinal axis of the cask. The skid also comprises a retaining member including parallel spaced-apart plates. The plates of the retaining member are aligned perpendicular to a longitudinal axis of the cask, include a trough for mating with the cask, and are connected by longitudinal fins parallel to the longitudinal axis of the cask. The fins of the supporting member are spaced apart such that when the cask rests in the trough of the supporting member, the fins of the supporting member are aligned with elongate members of the cask neutron radiation shielding material to transfer the load between the cask and the skid.

Abstract: The present invention provides a cask (10) for transport and short-term storage of spent nuclear fuel. The cask 10 includes a structural shell (14) defining a cavity (40) for receiving spent nuclear fuel. The shell is formed from an upper shell portion (16) formed of a first metal-and a lower shell portion (18) formed from a second metal. The first metal utilized to form the upper shell portion has a higher load bearing strength than the second metal utilized to form the lower shell portion. A bearing surface is defined on the upper shell portion by trunnions (30) mounted within sleeves (32) secured to the upper shell portion. The trunnions (30) each define a bearing projection (160) that is engageable to enable hoisting of the cask, with the tensile and shear loads of hoisting the cask being transferred from the trunnions to the trunnion mounting sleeves, and thus to the upper shell portion of the structural shell.

Abstract: Impact limiters having noncircular outer peripheries are described for use to protect nuclear fuel transportation casks. The impact limiters include two different materials as impact absorbing materials. The impact limiter includes multiple sides and a tapered cap.

Abstract: A method of predictably dewatering a slurry that contains radioactive particles to a condition for safe permanent storage. Interstitial water is removed from the slurry, and then a sufficient quantity of adsorbed water is removed from the particles so that at the permanent storage temperature the particles will be just unsaturated with respect to adsorbed water. The dewatering endpoint is set to at least unsaturate the particles at the permanent storage temperature. This minimum volume of adsorbed water removal is necessary to assure the subsequent uptake of any condensed water that develops during storage in a sealed container. An upper dewatering endpoint is preferably set so that the volume of adsorbed water removed from the particles does not excessively unsaturate the particles, so that the sealed storage container that eventually confines the dewatered particles will not burst if the particles later become exposed to ambient water or water vapor.

Abstract: Disclosed is a method of installing a reversibly porous, air-diffusible, water-restrictive, polymer plug in a port that extends through the wall of a nuclear waste storage container. The plug is inserted a predetermined distance, for example, with the aid of a screwdriver applied to a slot in the plug's outer face. When inserted, the plug prevents the loss of nuclear waste through the port while the air-diffusible nature of the material allows gases to pass through the material. The resultant venting action of the plug prevents the creation of pressure differences between the interior of the container and the environment. Thus, the likelihood of the container becoming overpressurized and leaking is minimized. In addition, the water-restrictive nature of the plug material restricts the ingress and egress of water from the container, reducing the likelihood of groundwater contamination during storage.