The Transportation of Spent Nuclear Fuel and High-Level Radioactive Waste
A Systematic Basis for Planning and Management at the National, Regional, and Community Levels
Planning Information Corporation
The assessment of shipment groups (section 5) determines the assemblies and MTU to be picked up for shipment from a particular storage location in a particular acceptance year. The identification of cask options (section 6) determines the transportation casks available under the particular scenario, and the transportation choice assessment (sections 7 through 11) determines the cask option selected for shipment from each storage location.
The next step in the assessment process is to determine the number of cask shipments from each storage location in each acceptance/pickup year.
Cask shipments of spent fuel from BWR or PWR reactors are estimated by dividing the number of assemblies in the shipment group by the assembly capacity of the selected cask—rounding up to accommodate any fractions required to ship all assemblies in the group.
Cask shipments of other spent fuel (e.g., spent fuel from research reactors or HTG assemblies from the Fort St. Vrain reactor) are estimated by dividing the MTU in the shipment group by the average MTU per cask for BWR and PWR assemblies shipped during the same period—generally about .40 MTU per T-1/2 cask, 1.655 MTU per T-4/9 cask, 4.28 MTU per R75 cask and 7.41 MTU per R125 cask. In effect, the assumption is that casks for HTG, research and other wastes will be as efficient as those designed for transport of BWR and PWR assemblies.
Cask shipments for HLW assume that an MPC-like cask to accommodate five two-foot diameter canisters will be designed and certified for transport of HLW. The estimated shipments of HLW canisters from a particular site is thus divided by five—rounding up to accommodate any remaining canisters in the shipment group.