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AssigneeGNS Gesellschaft fur Nuklear-Service mbH
InventorsHenning Baatz, Dieter Rittscher, Jurgen Fischer
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A container for the transport, storage and disposal of radioactive wastes or other materials, such as irradiated fuel elements of a nuclear reactor capable of neutron emission, which comprises a cast receptacle, e.g. of cast iron, a cover and, in passages spaced apart in the cast wall of the vessel, a neutron moderating or absorbing material. According to the invention, the passages are of circular cross section with a spacing at least equal to twice the diameter, and the total cross-sectional area of the passages in any plane transversely through the vessel corresponds to the cross section in the same plane of a continuous theoretical layer disposed along the periphery of a vessel of corresponding thickness and size or is greater than the area of the theoretical layer in this plane in so far as neutron absorption or moderation effect is concerned. The moderator passages thus provide a total volume which can correspond to the volume of the theoretical layer applied externally of the wall of the vessel and for a given moderator material will have the same moderation or absorption effect.
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.
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;
Dependencies are inferred from the claim text.