Abstract: The invention is an apparatus and method for on-line sorting of waste matter, at the entrance to a waste processing plant, according to the level of specific chemicals, typically chlorine detected therein. The apparatus comprises a waste matter inlet that provides waste matter to a weighing module, preferably until a preset limit is reached. Then, this control volume of waste is introduced into a pulsed neutron material analyzer that is optimized for the determination of the content of the specific chemical in the control volume. A control means such as a computer then decides whether the level of the chemical in the waste control volume is above or below a preset threshold, and accordingly channels the waste into one or another of two channels. One of these channels accepts waste with low content of the given chemical, for introduction into the waste processing chamber.

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.

Abstract: Neutron activation is used to analyse the silicon and aluminium content of samples of material, such as bauxite ore and coal. The analysis can be performed on bulk samples, on material on a moving conveyor belt, or on the walls of a borehole. The method involves high energy neutron irradiation of the sample, measurement of the thermal neutron flux in the sample, and monitoring the gamma radiation from the sample at energies of (a) 1.78 MeV and (b) 0.844 MeV and/or 1.015 MeV. Such gamma radiation is produced on decay of (a) .sup.28 Al and (b) .sup.27 Mg isotopes, produced by the reactions .sup.28 Si(n,p).sup.28 Al and .sup.27 Al(n,p).sup.27 Mg. A single gamma ray detector is used. The analysis preferably utilizes equations which include terms to compensate for (a) the production of radiation at 1.78 MeV as a result of the production of the isotope .sup.28 Al from .sup.27 Al by the thermal neutron reaction .sup.27 Al(n,.gamma.).sup.28 Al, and (b) the Compton scattering of 1.