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| DOE-STD-3028-2000
Appendix A. Technical Bases for 233U Packaging and Storage Criteria
This Appendix summarizes the technical bases for the criteria in this Standard. Section numbers
in this Appendix correspond to the section numbers in the body of the Standard and provides
guidance where applicable. The reader is directed to the primary technical source information
and the 233U Technical Handbook [Storch 1999] for further details.
Development of this Standard was modeled on the Standard for plutonium [DOE 1999].
Although plutonium and uranium have significant physical/chemical differences, many of the
storage issues are similar. Consequently, this Standard makes use of plutonium studies for
issues that are material independent or for issues where the plutonium behavior bounds the 233U
behavior (e.g., alpha radiolysis).
A.1
PURPOSE AND SCOPE
This Standard establishes criteria for packaging, and long-term safe storage of separated 233U-
bearing metals and oxides. Storage packages that meet these criteria should maintain their
integrity (i.e., should not require further repackaging) for a minimum of 50 years. The bulk of
these materials are stored at ORNL and INEEL as solid forms including metals, oxide powders,
ceramic oxide pellets, and oxide monoliths. This Standard does not apply to 233U-bearing
liquids, residues, wastes, spent fuels, irradiated targets, in-process materials or small quantities
involved in research and development studies. Those materials are either addressed by other
storage programs or are not germane to the intended safe storage activity.
With the exception of oxide from the Consolidated Edison Uranium Solidification Project
(CEUSP) , the material covered by this Standard is nearly isotopically pure 233U with trace
include 238U (4.5 x 109 y), 236U 2.4 x 107 y), 235U (7.0 x 108 y), 234U (2.4 x 105 y),
233
U (1.6 x 105 y), and 232U (69 y). Uranium-233 and its associated isotope 232U are man-made.
They present potentially more severe radiological hazards than the naturally occurring uranium
enriched uranium (HEU) is the 233U isotopic concentration at which the specific activity of 233U
exceeds that for uranium highly enriched in the 235U isotope [Bereolos et al. 1998]. Any 232U
present will lower this bound even further.
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