Patent Number: 042886988
Section: claims

1. A transport and storage vessel for radioactive material, especially nuclear power plant waste, comprising a cast receptacle of a gamma-radiation shielding material having vertical walls defining a compartment for receiving said radioactive material, a bottom and a cover closing said compartment, at least said vertical walls being formed with spaced apart longitudinal passages of circular section with a spacing between said passages being equal to at least twice the diameter of said passages, a neutron moderator filling said passages, the volume of said neutron moderator in said passages being at least equal to the volume of an imaginary layer of said material applied along the exterior of an equivalent vessel to achieve a predetermined attenuation of neutron emission. 2. The transport and storage vessel for radioactive materials defined in claim 1 wherein said neutron moderator is water. 3. The transport and storage vessel for radioactive materials defined in claim 1 or claim 2 wherein said cover is formed with chambers receiving said moderator material. 4. The transport and storage vessel for radioactive materials defined in claim 1 or claim 2 wherein said bottom is provided with chambers receiving said moderator material. 5. The transport and storage vessel for radioactive materials defined in claim 3 wherein said cover is provided with a plate closing said chambers. 6. The transport and storage vessel for radioactive materials defined in claim 4 wherein said bottom is provided with a plate closing said chambers. 7. The transport and storage vessel for radioactive materials defined in claim 1 wherein said passages are provided in at least two rows about the periphery of said vessel and each passage is disposed in the spaces between passages of the other row. 8. A method of packaging for transport and storage radioactive materials especially nuclear power plant waste in a cast receptacle of a gamma-shielding material having vertical walls defining a compartment for receiving said radioactive materials, comprising the steps of determining the volume of a neutron moderator required to form an imaginary layer along the exterior of said vessel to achieve a predetermined attenuation of neutron emission beyond said vessel; forming said walls with spaced apart longitudinal passages of circular cross section with a spacing between said passages equal to at least twice the diameter of said passages; forming said passages in number and diameter such that the total volume of said passages is equal to said volume in said imaginary layer; filling said passages with said moderator; introducing said radioactive materials into said compartment; and closing said compartment with a cover.