Abstract: Method for analysis of the content of certain elements in a continuous flow of bulk materials by neutron bombardment and measurement of the gamma radiation emitted by such elements, which makes it possible to distinguish between the capture radiation and the activation radiation. The neutron source is a neutron-generating tube which is activated periodically. The signals from a single gamma radiation detector are considered only after neutron emission has ceased, during distinct intervals corresponding to the phenomena of capture and radiation of the activated elements, respectively. The respective signals are treated in two distinct measurement routes, and the measurements are then combined automatically. A third measurements route can be provided for gamma radiation resulting from inelastic collisions. The source and the detector are positioned in a probe lodged in a polyethylene protective tube within the flow of the materials.