[Energy Solutions] Task Order 17- Spent Nuclear Fuel Transportation Cask Design Study

Per the requirements of the Task Order 17: Spent Nuclear Fuel Transportation Cask Design Study, statement of work (SOW), EnergySolutions and its team partners: NAC International,
Talisman International, Booz Allen Hamilton and Exelon Nuclear Partners, hereafter referred to as “the Team,” is providing a final report for U.S. Department of Energy (DOE) review, which documents the cask concepts developed under this study and the results of supporting analysis work.

The base cask concept is a 125-ton (maximum), single lid cask designed to accommodate an overall fuel assembly heat generation level of up to 24 kW. Pressurized Water Reactor (PWR) and Boiling Water Reactor (BWR) designs have two fuel basket capacities each, which are 32 bare PWR assemblies (32-PWR) or 28 PWR assemblies in Damaged Fuel Cans (DFCs) (28-PWR), and 68 bare BWR assemblies (68-BWR) or 61 BWR (61-BWR) assemblies in DFCs, respectively. All of the DFC designs have slightly lower capacity, since the DFCs are larger than bare fuel assemblies and require lower-capacity baskets that have larger cell openings. The PWR and BWR bare fuel designs are also able to accommodate combinations of 8 PWR assemblies in DFCs and 24 bare PWR assemblies, and 8 BWR assemblies in DFCs and 60 bare BWR assemblies, respectively. For high burn-up, shorter cooled spent nuclear fuel (SNF), the numbers of fuel assemblies is more restricted. Assuming that there is no other fuel in the basket, up to twelve (12) 62.5 GWd/MT PWR assemblies with out-of-reactor cooling time of 5 years can be transported in either the 32-PWR or 28-PWR designs. The 68-BWR, depending on assembly uranium loading and enrichment, can transport up to thirty-two (32) 62.5 GWd/MT BWR assemblies with out-of-reactor cooling times of 5 years. The 61-BWR, again depending on assembly uranium loading and enrichment, can transport up to twenty-nine (29) 62.5 GWd/MT BWR assemblies with out-of-reactor cooling times of 5 years.

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