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Probability of a PWR Uncanistered Fuel Waste Package Postclosure Criticality

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BBA000000-01717-0210-00010_MOL.19980806.0607.pdf (2.55 MB) 2.55 MB
Abstract

The purpose of this calculation is to estimate the probability of criticality in a pressurized water reactor (PWR) uncanistered fuel waste package during the postclosure phase of the repository as a function of various waste package material, loading, and environmental parameters. Parameterization on the upper subcritical limit that is used to define the threshold for criticality will also be performed. The possibility of waste package misload due to human or equipment error during preclosure is also considered in estimating the postclosure criticality probability.

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