Quantcast Criticality Safety Evaluation for Shipment of Radioactive Waste within the Boundaries of the INEL

 

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DOE-STD-3007-93
Criticality Safety Evaluation for
Shipment of Radioactive
Waste within the Boundaries of the INEL
Shipments of radioactive waste within the boundaries of the INEL are made in a variety of
shipping casks. The purpose of this report is to establish appropriate limits and demonstrate that
these limits are in compliance with the criticality safety requirements stated in DOE-ID 5480.5A1
and 10 CFR Part 712, Sections 71.55 and 71.61, for a Fissile Class III shipment.
Shipments of radioactive waste may be made within the boundaries of the INEL in several
different types of shipping casks. One such cask, TRUPACT-II, is licensed for Fissile Class I
shipments with up to 325 Fissile Gram Equivalent (FGE) of Pu-2393. Any number of
TRUPACT-II packages may be simultaneously transported.
Other shipping casks that do not have formally established fissile material limits may also
be used to make waste shipments, one-cask-at-a-time, with no more than 160 FGE of Pu-239 per
shipment. Loading of a second cask will not take place until the first cask is removed from the
area. The casks involved are typically constructed of concentric regions of lead and steel or
depleted uranium and steel. Limits for shipments involving these casks will be conservatively
based on generic minimum critical mass data. Therefore, details of the various cask designs are
not pertinent. However, if the limits identified in this evaluation are to be exceeded, an evaluation
specific to the cask shall be required.
[Note: The description section of this example evaluation does not include the level of detail (i.e.,
cask dimensions and sketches) that would normally be found in an evaluation due to the generic
nature of the evaluation.]
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