Abstract
Radiation detection systems are deployed at U.S. borders to guard against entry of illicit radioactive material. This article uses realistic simulated data under different vehicle and illicit material scenarios to compare the performance of six detection methods for analyzing neutron count data collected as a vehicle passes through a radiation portal monitor, that is, a neutron count vehicle profile. The six methods are based on the cumulative count, the maximum count, sequential cumulative sum, sequential exponentially weighted moving average, comparison against a matched filter (MF) library, and a new estimated MF that estimates the shape of a neutron count vehicle profile.
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