Patent Number: 
Section: claims

1. An inner canister for use with an outer cask in a dry nuclear component handling arrangement, the inner canister comprising a canister housing configured to store a quantity of irradiated nuclear plant components or high level waste therein, the canister housing having an outer envelope configured to fit within an interior profile of the outer cask, wherein the inner canister comprises one of either: a first canister comprising a plurality of heat dissipation elements or a second canister comprising a plurality of components devoid of neutron absorbing materials. 2. The inner canister of claim 1, wherein the inner canister comprises the first canister, wherein the canister housing comprises an exterior wall, and wherein the plurality of heat dissipation elements comprise a plurality of heat dissipation fins extending radially outwardly from the exterior wall. 3. The inner canister of claim 2, wherein the exterior wall has a top and a bottom disposed opposite and distal the top; and wherein at least a majority of the plurality of heat dissipation fins extends longitudinally from proximate the top to proximate the bottom. 4. The inner canister of claim 2, wherein the exterior wall is substantially cylindrical-shaped; and wherein the plurality of heat dissipation fins are substantially evenly spaced from one another along the exterior wall. 5. The inner canister of claim 1, wherein the inner canister comprises the second canister, wherein the canister housing comprises an interior volume and the plurality of components are housed therein. 6. The inner canister of claim 1, wherein the inner canister comprises the second canister, and wherein the plurality of components comprise a plurality of fuel cell walls devoid of neutron absorbing materials. 7. A dry nuclear component handling arrangement:an outer cask having a cask housing defining an interior envelope; andan inner canister having a canister housing configured to store a quantity of irradiated nuclear plant components or high level waste therein, the canister housing having an outer envelope configured to fit within the interior envelope of the outer cask,wherein the inner canister comprises one of either: a first canister comprising a plurality of heat dissipation elements or a second canister comprising a plurality of components devoid of neutron absorbing materials. 8. The dry nuclear component handling arrangement of claim 7, including a vent and duct system between the inner canister and the outer cask configured to remove heat from the inner canister. 9. The dry nuclear component handling arrangement of claim 8 wherein the vent and duct system comprises:an intake in a lower portion of the outer cask,an outlet in an upper portion of the outer cask, anda duct defined between an inner side of the outer cask and an outer side of the inner canister and extending between the intake and the outlet. 10. The dry nuclear component handling arrangement of claim 9, wherein the inner canister comprises the first canister, wherein the canister housing comprises an exterior wall, and wherein the plurality of heat dissipation elements comprise a plurality of heat dissipation fins extending radially outwardly from the exterior wall into the duct. 11. The dry nuclear component handling arrangement of claim 10, wherein the inner canister is an enhanced surface area canister shape having an inner concentric canister wall within, spaced from, and concentric with the exterior wall; wherein the inner canister further includes a plurality of heat dissipation fins that extend inwardly in a generally radial direction into a generally open space surrounded on a side by the inner concentric canister wall and open to an external environment. 12. The dry nuclear component handling arrangement of claim 9, wherein the duct is an annular passage between the outer cask and the inner canister. 13. The dry nuclear component handling arrangement of claim 7, wherein the envelope of the inner canister is pressurized with helium. 14. The dry nuclear component handling arrangement of claim 13, wherein the pressure of the helium is either proximate atmospheric pressure or greater than atmospheric pressure. 15. The dry nuclear component handling arrangement of claim 7, wherein a wall of the inner canister comprises a composite matrix metal structural material. 16. The dry nuclear component handling arrangement of claim 15, wherein the composite matrix metal structural material is a metal matrix composite. 17. The dry nuclear component handling arrangement of claim 7, including an active cooling system for cooling the inner canister during loading of the irradiated nuclear plant components or high level waste therein. 18. A dry nuclear component canister system comprising:an outer cask system comprising a plurality of outer casks including a storage overpack, a transfer cask and a transportation cask, with each of the outer casks having a similar interior profile; andan inner canister system comprising a plurality of inner canisters, each inner canister configured to store an irradiated nuclear plant component or high level waste, each inner canister having an outer envelope that fits within the interior profile of the outer casks. 19. The dry nuclear component canister system of claim 18, wherein the plurality of inner canisters comprises a canister comprising a plurality of components devoid of neutron absorbing materials. 20. The dry nuclear component canister system of claim 18, wherein the plurality of inner canisters comprises a canister comprising a plurality of heat dissipation elements. 21. The inner canister of claim 1, wherein the neutron absorbing materials comprise boron.