Patent Number: 
Section: claims

1. A heat transfer cask comprising:shielding defining an internal cavity and limiting ionizing radiation from passing from the cavity to an environment surrounding the heat transfer cask;a heat transport path including a heat pipe extending from inside the shielding to outside the shielding;a heater to warm the cavity; anda convection jacket surrounding the cavity, wherein the convection jacket is configured to distribute heat evenly within the cavity, and wherein the heater extends into the convection jacket. 2. The cask of claim 1, wherein the heat transport path includes a directional change through the shielding to block the ionizing radiation. 3. The cask of claim 1, further comprising:nuclear material contained within the cavity, wherein the nuclear material is at least one of fresh nuclear fuel, spent nuclear fuel, radiation sources, irradiated waste, and radioactive-contaminated waste. 4. The cask of claim 3, wherein the heat transport path is configured to transport heat outside the cask so that the cavity does not exceed 650° C. 5. The cask of claim 4, wherein the heat transport path includes at least 20 1 kW heat pipes. 6. The cask of claim 1, further comprising:a damper enclosure at an end of the cask, wherein the heat transport path extends into the damper enclosure, and wherein the damper enclosure can be opened to enhance fluid convection about the heat transport path and closed to limit fluid convection about the heat transport path. 7. The cask of claim 1, further comprising:a convection jacket surrounding the cavity, wherein the convection jacket is configured to distribute heat evenly within the cavity. 8. The cask of claim 7, wherein the convection jacket contains only metal sodium configured to melt and circulate to distribute the heat evenly within the cavity. 9. The cask of claim 7, wherein the heat transport path has an end in the convection jacket. 10. The cask of claim 1, further comprising:a damper enclosure at an end of the cask, wherein the heat transport path extends from the convection jacket into the damper enclosure, and wherein the damper enclosure can be closed to limit fluid convection about the heat transport path when the heater is heating the convection jacket. 11. A heat transfer cask for storing nuclear material below 650° C., the cask comprising:shielding defining an internal cavity and limiting ionizing radiation from passing from the cavity to an environment surrounding the heat transfer cask; anda heat transport path having a first closed end inside the shielding to and a second closed end outside the shielding such that no fluid exits the heat transport path, wherein the heat transport path is shaped so that no straight line passes through both the first and the second ends of the heat transport path and not the shielding, and wherein the cask is fabricated only of materials configured to maintain their chemical identities when exposed to ionizing radiation from spent nuclear fuel. 12. The heat transfer cask of claim 11, wherein the heat transport path is at least one of a heat pipe and a solid conductive rod. 13. The heat transfer cask of claim 11, further comprising:a convection jacket surrounding the cavity, wherein the heat transport path extends into the convection jacket, wherein the convection jacket is configured to melt by 200° C. and distribute heat evenly within the cavity. 14. The cask of claim 13, further comprising:a heater to warm the cavity, wherein the heater extends into the convection jacket. 15. A method of storing nuclear fuel in a heat transfer cask including, shielding defining an internal cavity and limiting ionizing radiation from passing from the cavity to an environment surrounding the heat transfer cask, a convection jacket surrounding the cavity and configured to melt by 200° C. and distribute heat evenly within the cavity, and a heat transport path from inside the shielding into the convection jacket and to outside the shielding, the heat transport path being shaped so that no straight line internal to the heat transport path passes through both ends of the heat transport path, the cask being fabricated only of materials configured to maintain their chemical identities when exposed to ionizing radiation from spent nuclear fuel, wherein the method comprises:loading fresh fuel from the internal cavity of the cask into a reactor; andunloading the spent fuel or nuclear material from the reactor into the internal cavity of the cask. 16. The method of claim 15, wherein the cask is not closed during or between the loading and unloading. 17. The method of claim 15, further comprising:activating a heater in the cask to warm the fresh fuel to at least 200° C.