Management of Commercially Generated Radioactive Waste - U.S. ...

4.44
treatment options at an FRP and at a MOX-FFP for the reprocessing cycle. Table 4.3.1 con-
tains a summary of the releases estimated for radionuclides of potential importance during
the treatment processes selected for use in this Statement. These release estimates are
given as the fraction of the quantity present in spent fuel that is released during the
treatment and packaging operations.
As mentioned earlier, tritium removal is not assumed in this Statement because the
technology has not been fully demonstrated. Should the voloxidation process described
earlier be successfully developed and applied, the release of tritium could be reduced to a
value only 1% (or less) as large as that listed here.
All of these releases to the environment occur in gaseous or airborne waste streams.
There are no planned discharges of radionuclide-contaminated liquid streams from these
facilities.
4.3.6 Treated Waste Quantities
Table 4.3.2 contains a summary of the ranges of quantities of treated and packaged
high-level, TRU, and gaseous wastes that result from implementation of various options of
the once-through or reprocessing cycles described in Sections 4.3.1 through 4.3.4. These
quantities are given in terms of the number of waste packages rather than in terms of the
volume of waste because, for the mined geologic repository concepts used in this Statement,
the repository area required for high-level waste is a function of the waste heat output
while the area required for remotely handled TRU wastes is a function of the number of con-
tainers rather than of the volume of waste (see Section 5.3). The data for the packaging
of intact fuel in the once-through case and for the packaging of the reprocessing wastes
were taken from DOE/ET-0028. The data for the packaging of processed spent fuel were taken
from ONWI-39.