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Structural credit for depleted uranium used in transport casks

Salzbrenner, R.; Wellman, G.W.; Sorenson, K.B.; Mcconnell, P.

Depleted uranium (DU) is used in high level radioactive waste transport containers as a gamma shield. The mechanical response of this material has generally not been included in calculations intended to assure that these casks will maintain their containment function during all normal use and accident conditions. If DU could be qualified as a structural component, the thickness of other materials (e.g. stainless steel) in the primary containment boundary could be reduced, thereby allowing a reduction in cask mass and/or an increase in payload capacity. This study was conducted to determine the mechanical behavior of a range of DU alloys in order to extend the limited set of mechanical properties reported in the literature. These mechanical properties were used as the basis for finite element calculations to quantify the potential for claiming structural credit for DU.