Compatibility of technologies with regulations in the waste management of H-3, I-129, C-14, and Kr-85. Part II. Analysis

Waste forms of 3H, 129I, 14C, and 85Kr separated from fuel reprocessing streams and procedures for managing them were analyzed regarding compliance with regulations. Transportation of these wastes in certain DOT-specification packagings would be permissible, but some of these packagings may not be acceptable in some disposal situations. Transportation of gaseous 85Kr in a currently certified cylinder is possible, but a fuel reprocessor may wish to ship larger quantities per package. Disposal of tritium using a package designed by a DOE contractor and shallow land burial, in accord with the regulations of 10 CFR 61, seems practicable. Although 10 CFR 61 permits shallow land burial of 129I, the concentration limit requires distribution in a volume that may seem impractical to commercial fuel reprocessors. The concentration limit of 10 CFR 61 for shallow land burial of 14C requires distribution in a lesser, although still large, volume. For both 129I and 14C, management as high-level waste offers the advantage of smaller volumes. Similar advantages may be offered by greater confinement or non-near surface concepts for disposal. The concrete waste forms developed for these nuclides may not meet technical criteria being formulated for geologic disposal. The lack of accommodation of 85Kr at disposal facilities makes storage of the gaseous form at the fuel reprocessing plant, followed by dispersal after partial decay, seem attractive. Ocean disposal of 129I and 14C by the rules of the International Atomic Energy Agency-London Ocean Dumping Convention offers advantages over shallow land burial: higher allowed concentrations, resulting in smaller volumes and fewer packages. These rules, however, thwart ocean disposal of 85Kr since gaseous forms are banned, and for solid forms, concentration limits would require distribution of radioactivity in very large volumes. 80 references