Differential radiological impact of plutonium recycle in light water reactors: transport in normal conditions

The aim of this study is to estimate the differential radiological impact of plutonium recycle in the fuel cycle of light water reactors for the transports in normal conditions between the different installations. For the UO2 fuel cycle, only the transports of spent fuels between the nuclear power plants and the reprocessing plants may involve an irradiation of populations. In the case of fuels U/MOX, three other types of transport have to be taken into consideration: the transports between the reprocessing plant and the fuel fabrication plant, the transports of fresh fuels from the fabrication plant to the nuclear power plants, and, the transports of plutonium wastes from the fabrication plant to the waste disposal centers. The annual effective dose equivalents of external irradiation induced by photons and neutrons, delivered to the riverain populations and to the passengers of other vehicles, have been estimated. This study points out the differential impact U/MOX-UO2 of 3,4.10-2. h.Sv.a-1, involved, for a great part, by the transport of spent fuels (1,99.10-2 h.Sv.a-1). The contribution of neutrons is about five times the one of photons. The annual effective dose equivalents received, the riverain populations and by the passengers of other vehicles have nearly the same value