A device for detecting neutron emission comprises a housing, a moderator structure, a neutron detection element, and a plurality of plate electrodes. The housing provides an enclosure and shielding from radiation other than neutron emission. The moderator structure is positioned within the housing and is formed from energy absorbing material. The moderator structure includes a first side wall and a second side wall spaced apart and oriented parallel to one another. The neutron detection element includes a neutron reactive material deposited on a planar substrate. The plate electrodes are formed from electrically conductive material and spaced apart from one another. Each adjacent pair of plate electrodes has a voltage therebetween, wherein one neutron detection element is positioned between adjacent pairs of plate electrodes and the combination of plate electrodes and neutron detection elements is positioned between the first side wall and the second side wall of the moderator structure.

A neutron activation detector comprises a first enclosure, a plurality of electrical leads, and an activation medium disposed within the enclosure. The activation medium consists substantially of a material that is activated by fast neutrons, and is arranged within the enclosure so that activation of the material by fast neutrons results in a current between the plurality of electrical leads.

A neutron activation detector comprises a first enclosure, a plurality of electrical leads, and an activation medium disposed within the enclosure. The activation medium consists substantially of a material that is activated by fast neutrons, and is arranged within the enclosure so that activation of the material by fast neutrons results in a current between the plurality of electrical leads.

A radiation dose quantification method and system, the method comprising: detecting, with one or more detectors with respective sensitive volumes, gamma-rays emitted as a result of capture of neutrons by a composition in a subject subjected to an irradiation program, the composition comprising one or more thermal neutron capture agents, the neutrons having been generated by non-elastic collisions between a primary beam of particles and nuclei in the subject, wherein the particles consist of any one or more of protons, deuterons, tritons and heavy ions, the irradiation program comprises at least one period of irradiation with a beam duration that includes beam-on periods and beam-off periods; applying at least one predefined energy window or filter configured to accept only detection events in the one or more detectors resulting from gamma-rays with an energy indicative of selected gamma-rays arising from the capture of thermal neutrons by the one or more thermal neutron capture agents, wherein the thermal neutrons are neutrons with energies below approximately 0.4 eV; applying a timing window configured to reject or ignore detection events in the one or more detectors resulting from at least prompt gamma-rays produced in non-neutron capture events; and determining the radiation dose of neutron radiation received by the subject during the irradiation program from at least the accepted detection events or determining a dose map of the radiation received by the subject from at least the accepted detection events.

A radiation dose quantification method and system, the method comprising: detecting, with one or more detectors with respective sensitive volumes, gamma-rays emitted as a result of capture of neutrons by a composition in a subject subjected to an irradiation program, the composition comprising one or more thermal neutron capture agents, the neutrons having been generated by non-elastic collisions between a primary beam of particles and nuclei in the subject, wherein the particles consist of any one or more of protons, deuterons, tritons and heavy ions, the irradiation program comprises at least one period of irradiation with a beam duration that includes beam-on periods and beam-off periods; applying at least one predefined energy window or filter configured to accept only detection events in the one or more detectors resulting from gamma-rays with an energy indicative of selected gamma-rays arising from the capture of thermal neutrons by the one or more thermal neutron capture agents, wherein the thermal neutrons are neutrons with energies below approximately 0.4 eV; applying a timing window configured to reject or ignore detection events in the one or more detectors resulting from at least prompt gamma-rays produced in non-neutron capture events; and determining the radiation dose of neutron radiation received by the subject during the irradiation program from at least the accepted detection events or determining a dose map of the radiation received by the subject from at least the accepted detection events.

To obtain a neutron detector capable of measuring high dose neutrons with high neutron/gamma-ray discrimination ability and high efficiency. A scintillator 10 has a layered structure in which a phosphor layer 11 and a light transmission layer 12 are alternately laminated in z direction. The phosphor layer 11 is made of a phosphor material emitting fluorescent light by absorbing neutrons, the material being, for example, a scintillator material used in neutron detectors having already been known. The light transmission layer 12 is made of a material highly transmitting fluorescent light emitted by the phosphor material and only slightly absorbing neutrons. In the scintillator 10, when neutrons and gamma-ray photons enter it, luminescence intensity (pulse height) due to neutrons is significantly different from that due to gamma-ray photons. It makes it easy to discriminate between outputs due to the two kinds of radiations.

To obtain a neutron detector capable of measuring high dose neutrons with high neutron/gamma-ray discrimination ability and high efficiency. A scintillator 10 has a layered structure in which a phosphor layer 11 and a light transmission layer 12 are alternately laminated in z direction. The phosphor layer 11 is made of a phosphor material emitting fluorescent light by absorbing neutrons, the material being, for example, a scintillator material used in neutron detectors having already been known. The light transmission layer 12 is made of a material highly transmitting fluorescent light emitted by the phosphor material and only slightly absorbing neutrons. In the scintillator 10, when neutrons and gamma-ray photons enter it, luminescence intensity (pulse height) due to neutrons is significantly different from that due to gamma-ray photons. It makes it easy to discriminate between outputs due to the two kinds of radiations.

Systems and Methods for an air slide analyzer for measuring the elemental content of aerated material traveling by air slide. The air slide analyzer has an analyzer having an entrance opening and an exit opening, and an interior tunnel adapted for aerated material conveyed by an air slide; a radiation detector proximal to the analyzer; a neutron source emitting neutrons into material within the analyzer; and a processor to analyze detected information from the radiation detector, wherein emissions from the material being irradiated with neutrons are detected by the radiation detector and analyzed by the processor to provide elemental information of the material in the analyzer.

Systems and Methods for an air slide analyzer for measuring the elemental content of aerated material traveling by air slide. The air slide analyzer has an analyzer having an entrance opening and an exit opening, and an interior tunnel adapted for aerated material conveyed by an air slide; a radiation detector proximal to the analyzer; a neutron source emitting neutrons into material within the analyzer; and a processor to analyze detected information from the radiation detector, wherein emissions from the material being irradiated with neutrons are detected by the radiation detector and analyzed by the processor to provide elemental information of the material in the analyzer.

Disclosed is a nanosecond neutron analysis and associated particle imaging system (NNA/API) and gamma ray detector arrangement (arrangement) that uses associative element detection of titanium, iron and oxygen to determine concentrations of ilmenite or other minerals in extra-terrestrial bodies associated with He-3. The arrangement is used with a mobile carrier for mapping out concentrations of likely He-3 regions on the extra-terrestrial body.