A method for a multielement analysis via neutron activation. The method includes generating fast neutrons with an energy in the range of 10 keV to 20 MeV and moderating the neutrons, irradiating the sample with the neutrons, and measuring the gamma radiation emitted by the irradiated sample using a detector to determine at least one element of the sample. The sample continuously irradiated in a non-pulsed fashion. The measurement is implemented during the irradiation. The determination of the at least one element includes an evaluation of the measured gamma radiation. The sample is subdivided into individual partitions and the measurement is implemented using a collimator. The evaluation includes a spatially resolved and energy-resolved determination of the neutron flux within the respective partition of the sample and calculation of energy-dependent photopeak efficiencies and neutron flux and neutron spectrum within a single partition of the sample by an approximation method.

A system for detecting gamma radiation by neutron activation of a material includes a switchable radiation source and at least a first detector. The switchable radiation source includes a primary source assembly having an alpha particle emitter, and a target assembly in which, upon irradiation of the target assembly by alpha particles from the primary source assembly, secondary radiation comprising neutrons is produced. An alignment, proximity or exposure of the primary source assembly relative to the target assembly is adjustable to control irradiation of the target assembly by the primary source assembly and thereby selectively irradiate a material under interrogation with the secondary radiation. The first detector is configured to detect gamma radiation prompted by neutron activation of the material under interrogation.

Multiple tagged neutrons are emitted from an associated particle imaging neutron generator. The tagged neutrons penetrate a target material and interact with the target material nucleuswhich emits nucleus-specific gamma rays. A gamma ray detector detects all gamma raysincluding the nucleus-specific gamma rays. An alpha-gamma timing spectrum is constructed for all detected gamma rays. For a specific energy level (MeV) corresponding with the target material nucleus, a peak in the alpha gamma timing spectrum indicates the presence of the target material. Based on the peaking time of the gamma rays (due to tagged neutrons interaction with the target material nucleus) in the alpha-gamma timing spectrum for the specific energy level, the distance from the neutron generator to the target material can be calculated. The nucleus-specific gamma ray spectrum data can be effectively collimated by programming the system to detect the gamma rays in a time window corresponding to the peaking time.

Material analysis device (100) comprising a neutron generator (10) for emitting neutrons towards a material to be analysed in pulsed mode; an alpha particle detector (13) for locating the neutrons emitted in a given solid angle by detecting alpha particles associated with these neutrons; at least one gamma ray detector (14) for measuring energy of gamma photons generated by interaction of the neutrons emitted in the given solid angle with the material to be analysed; at least two Compton cameras (15), each for measuring energy of the gamma photons generated by interaction of the neutrons with the material to be analysed and for calculating an incidence cone of these gamma photos; and an electronic circuit adapted for three-dimensionally mapping the presence of at least one chemical element of interest in the material to be analysed based on data provided by the alpha particle detector (13), the gamma ray detector (14) and the Compton cameras (15).

An apparatus for bulk ore sorting using gamma activation analysis is disclosed. The apparatus includes a conveyor system that includes one or more conveyor belts, surrounded by one or more radiation shields, to transport ore material along a transport path. A pulsed X-ray radiation source is configured to irradiate ore material at an irradiation region and one or more detectors are configured to detect a gamma radiation output from irradiated ore material at a detection region. The transport path has a bend, located between the irradiation region and the detection region, and about a vertical axis, of at least 45 degrees. The one or more detectors are configured to detect a radiation output from the irradiated ore material at times between X-ray pulses of the pulsed X-ray radiation source irradiating the ore material.

A system according to an exemplary aspect of the present disclosure includes, among other things, a generator-detector configured to be attached to a pipe. The generator-detector is configured to measure the concentration of mercury in the pipe in a non-destructive manner. A method is also disclosed.

A system according to an exemplary aspect of the present disclosure includes, among other things, a generator-detector configured to be attached to a pipe. The generator-detector is configured to measure the concentration of mercury in the pipe in a non-destructive manner. A method is also disclosed.

A nondestructive inspection system 1 is provided with: a neutron radiation unit 10 capable of radiating a first neutron dose of neutrons; a neutron detection unit 20 capable of detecting a second neutron dose of neutrons scattered inside an inspection object A upon radiation of neutrons from the neutron radiation unit 10; a gamma ray detection unit 30 capable of detecting a gamma ray dose released from the inspection object A upon radiation of neutrons from the neutron radiation unit 10; and an analysis unit 50 that calculates the contained amount of a predetermined substance on the basis of the gamma ray dose and corrects the contained amount of the predetermined substance on the basis of the first neutron dose and the second neutron dose.

Material analysis device (100) comprising a neutron generator (10) for emitting neutrons towards a material to be analysed in pulsed mode; an alpha particle detector (13) for locating the neutrons emitted in a given solid angle by detecting alpha particles associated with these neutrons; at least one gamma ray detector (14) for measuring energy of gamma photons generated by interaction of the neutrons emitted in the given solid angle with the material to be analysed; at least two Compton cameras (15), each for measuring energy of the gamma photons generated by interaction of the neutrons with the material to be analysed and for calculating an incidence cone of these gamma photos; and an electronic circuit adapted for three-dimensionally mapping the presence of at least one chemical element of interest in the material to be analysed based on data provided by the alpha particle detector (13), the gamma ray detector (14) and the Compton cameras (15).

A system for analyzing soil content of a field includes a data acquisition unit configured to detect gamma spectra of each of a plurality of soil samples, wherein a surface area of the field is divided into a plurality of portions and the plurality of soil samples comprises at least one soil sample from each of the plurality of portions, a navigation unit configured to detect geographic coordinates of each of the plurality of soil samples, a data analysis unit configured to associate the detected gamma spectra of each of the plurality of soil samples with the geographic coordinates of the soil sample and determine a weight percent of at least one element within each of the soil samples based on the detected gamma spectra, and an element content map unit configured to generate a map indicating concentration of the at least one element within the soil of the field.