Patent Number: 048250880
Section: claims

1. An improved cask assembly for containing radioactive materials, comprising a container having a shielding wall substantially formed from a radiation shielding material, and structural walls formed at least in part by titanium for supporting said shielding wall. 2. An improved cask assembly as defined in claim 1, wherein said shielding wall includes depleted uranium. 3. An improved cask assembly as defined in claim 1, wherein said shielding wall includes lead. 4. An improved cask assembly as defined in claim 1, wherein said shielding wall includes particles of boron suspended in a matrix of silicone. 5. An improved cask assembly as defined in claim 1, wherein said shielding wall includes tungsten. 6. An improved cask assembly as defined in claim 1, wherein said structural walls include an inner wall and an outer wall, and wherein said shielding wall is disposed between said inner and outer walls. 7. An improved cask assembly as defined in claim 6, wherein said structural walls further include a reinforcing ring also formed at least in part by titanium for interconnecting one end of said inner and outer walls. 8. An improved cask assembly as defined in claim 7, wherein said structural walls further include an end plate assembly also formed at least in part by titanium for interconnecting the other end of said inner and outer walls. 9. An improved cask assembly as defined in claim 6, wherein said inner wall and outer wall are substantially formed from a titanium alloy. 10. An improved cask assembly as defined in claim 6, wherein the inner wall is thick enough to support the shielding wall, yet thin enough to provide a minimum distance between radioactive materials disposed within the interior of the container and the shielding wall. 11. An improved cask assembly for containing radioactive materials, comprising a cylindrical container having a shielding wall substantially formed from a radiation shielding material, and structural walls including inner and outer walls circumscribing the inner and outer surfaces of the shielding wall for supporting said shielding wall, wherein said structural walls are formed substantially from a titanium alloy. 12. An improved cask assembly as defined in claim 11, wherein the inner wall is thick enough to support the shielding wall, yet thin enough to provide a minimum distance between the radioactive materials disposed within the interior of the container and the shielding wall. 13. An improved cask assembly as defined in claim 11, wherein the shielding wall is formed substantially from depleted uranium. 14. An improved cask assembly as defined in claim 11, wherein the shielding wall is formed substantially from lead. 15. An improved cask assembly as defined in claim 11, wherein the shielding wall is formed substantially from tungsten. 16. An improved cask assembly as defined in claim 11, wherein the shielding wall is formed substantially from particles of boron suspended in a matrix of silicone. 17. An improved cask assembly as defined in claim 11, wherein a reinforcing ring also formed substantially from a titanium alloy for interconnecting one end of said inner and outer walls. 18. An improved cask assembly as defined in claim 17, wherein said structural walls further include an end plate assembly also formed substantially from a titanium alloy for interconnecting the other end of said inner and outer walls. 19. An improved cask assembly as defined in claim 18, wherein said end plate assembly includes a layer of shielding material. 20. An improved cask assembly as defined in claim 19, wherein said layer of shielding material is formed from particles of boron suspended in a matrix of silicone. 21. An improved cask assembly for containing and transporting radioactive material of the type required to meet selected minimum strength and maximum weight criteria, comprising a cylindrical container structure having at least one shielding wall substantially formed from a radiation shielding material, inner and outer structural walls circumscribing the inner and outer surfaces of the shielding wall respectively, for supporting said shielding wall and for providing structural strength to the cask assembly, the interior of the cask assembly being defined by the inner wall, wherein said inner wall is substantially formed from a titanium alloy so that the thickness of said wall may be minimized, thereby minimizing the distance between the shielding wall and the radioactive wastes disposed in the interior of the cask assembly, and wherein the outer wall is also substantially formed from a titanium alloy in order to achieve said selected strength criteria with a minimum weight of wall material. 22. An improved lightweight cask assembly as defined in claim 21, further including a second shielding wall substantially formed from a radiation shielding material whose interior surface circumscribes the outer wall, and further including a second outer wall whose interior surface circumscribes the exterior surface of the second shielding wall, wherein the second outer wall is also substantially formed from a titanium alloy. 23. An improved lightweight cask assembly as defined in claim 22, wherein the first shielding wall is substantially formed from depleted uranium for absorbing gamma radiation. 24. An improved lightweight cask assembly as defined in claim 22, wherein said second shielding wall is substantially formed from a matrix of boron particles suspended in a matrix of silicone for absorbing neutrons. 25. An improved cask assembly for containing and transporting radioactive material of the type required to meet selected minimum strength and maximum weight criteria, comprising a cylindrical container structure having first and second shielding walls formed from depleted uranium and boron particles suspended in a matrix of silicone, respectively, and structural walls formed substantially from titanium including an outer wall, an intermediate wall and an inner wall, a reinforcing ring and an end plate assembly, wherein said first shielding wall is disposed between and supported by said inner and intermediate structural walls, and said second shielding wall is disposed between and supported by said intermediate and outer structural walls, the thickness of said inner wall being the minimum necessary to support said first shielding wall and achieve said strength criteria in order to minimize the distance between radioactive materials disposed in the interior of the cylindrical container structure and said first shielding wall, and wherein one end of said inner, outer and intermediate walls is joined together by said reinforcing ring, and wherein the other end of said inner, outer and intermediate walls is joined together by said end plate assembly. 26. An improved cask assembly as defined in claim 1, wherein said structural walls are formed from Ti-3-Al-2.5-V. 27. An improved cask assembly as defined in claim 11, wherein said structural walls are formed from Ti-3-Al-2.5-V. 28. An improved lightweight cask assembly as defined in claim 21, wherein said structural walls are formed from Ti-3-Al-2.5-V. 29. An improved cask assembly for containing and transporting a maximum amount of radioactive material in a cask structure of a selected maximum weight, minimum impact strength and maximum surface radiation, comprising a shielding wall formed from depleted uranium, and inner and outer structural walls circumscribing the inner and outer surfaces of the shielding wall for supporting said shielding wall, said inner wall defining the interior of the cask assembly where the radioactive material is contained, wherein the inner structural wall is substantially formed from a titanium alloy so that said minimum impact strength of said cask assembly may be achieved with an inner wall of minimum thickness, thereby minimizing the distance between said radioactive waste contained in the interior of the cask assembly and said shielding wall, and wherein said outer structural wall is also substantially formed from a titanium alloy so that said minimum impact strength may be achieved with a minimum amount of weight of wall material. 30. An improved cask assembly as defined in claim 29, wherein said inner and outer structural walls are formed from Ti-3-Al-2.5-V.