APPLICATION OF THE RADTRAN 5 STOP MODEL

A number of environmental impact analyses with the RADTRAN computer code have shown that dose to persons at stops is one of the largest components of incident-free dose during overland carriage of spent fuel and other radioactive materials (e.g., USDOE, 1994 ). The input data used in these analyses were taken from a 1983 study that reports actual observations of spent fuel shipments by truck (Madsen and Wilmot, 1983). Early RADTRAN stop models, however, were insufficiently flexible to take advantage of the detailed information in the study. A more recent study of gasoline service stations that specialize in servicing large trucks, which are the most likely stop locations for shipments of Type B packages in the United States, has provided additional, detailed data on refueling/meal stops (Griego et al., 1996). The RADTRAN 5 computer code for transportation risk analysis (Neuhauser and Kanipe, 1995) allows exposures at stops to be more fuJly modeled than have previous releases of the code and is able to take advantage of detailed data. It is the intent of this paper first to compare results from RADTRAN 4 (Neuhauser and Kanipe, 1992) and RADTRAN 5 for the old, low-resolution form of input data, and then to demonstrate what effect the new data and input format have on stop-dose estimates for an individual stop and for a hypothetical shipment route. Finally, these estimated public doses will be contrasted with doses calculated for a special population group - inspectors.