A non-destructive inspection system 1 includes a neutron detecting unit 4 and an arithmetic unit 60. The neutron detecting unit 4 includes a collimator 30 and a neutron detector 20 integrated together. The collimator 30 has a wall defining a through passage P. The wall is made from a material that absorbs neutrons produced via an inspection object. The neutron detector 20 is capable of detecting neutrons that have passed through the collimator 30. The arithmetic unit 60 generates information on a position and composition of the inspection object, based on information on the neutrons detected by the neutron detector 20, positional information indicating the position of the neutron detecting unit 4, and posture information indicating the posture of the neutron detecting unit 4. The positional information and the posture information are detected by a position and posture detecting unit 5.

A non-destructive inspection system 1 includes a neutron detecting unit 4 and an arithmetic unit 60. The neutron detecting unit 4 includes a collimator 30 and a neutron detector 20 integrated together. The collimator 30 has a wall defining a through passage P. The wall is made from a material that absorbs neutrons produced via an inspection object. The neutron detector 20 is capable of detecting neutrons that have passed through the collimator 30. The arithmetic unit 60 generates information on a position and composition of the inspection object, based on information on the neutrons detected by the neutron detector 20, positional information indicating the position of the neutron detecting unit 4, and posture information indicating the posture of the neutron detecting unit 4. The positional information and the posture information are detected by a position and posture detecting unit 5.

A neutron detector system for discriminating fissile material from non-fissile material wherein a digital data acquisition unit collects data at high rate, and in real-time processes large volumes of data directly to count neutrons from the unknown source and detecting excess grouped neutrons to identify fission in the unknown source. The system includes a Poisson neutron generator for in-beam interrogation of a possible fissile neutron source and a DC power supply that exhibits electrical ripple on the order of less than one part per million. Certain voltage multiplier circuits, such as Cockroft-Walton voltage multipliers, are used to enhance the effective of series resistor-inductor circuits components to reduce the ripple associated with traditional AC rectified, high voltage DC power supplies.

A neutron detector system for discriminating fissile material from non-fissile material wherein a digital data acquisition unit collects data at high rate, and in real-time processes large volumes of data directly to count neutrons from the unknown source and detecting excess grouped neutrons to identify fission in the unknown source. The system includes a Poisson neutron generator for in-beam interrogation of a possible fissile neutron source and a DC power supply that exhibits electrical ripple on the order of less than one part per million. Certain voltage multiplier circuits, such as Cockroft-Walton voltage multipliers, are used to enhance the effective of series resistor-inductor circuits components to reduce the ripple associated with traditional AC rectified, high voltage DC power supplies.

The present application relates to a detection structure for fast neutrons and a method for acquiring a neutron energy spectrum, the detection structure for fast neutrons comprises seven semiconductor detection units and a conversion layer made of a hydrogen-containing material, the seven semiconductor detection units comprise a first, a second, a third, a fourth, a fifth, a sixth and a seventh semiconductor detection unit arranged sequentially, the first, the fourth and the seventh semiconductor detection unit constitute an anticoincidence detection group, the second and the third semiconductor detection unit constitute a neutral particle background detection group, the fifth and the sixth semiconductor detection unit constitute a recoil proton detection group, the conversion layer is disposed between the fourth and the fifth semiconductor detection unit, incident neutrons collision with hydrogen atomic nuclei and generate the recoil protons. The present application can effectively reduce influence of background signals on the measurement and improve accuracy of the inversed neutron energy spectrum.

This application discloses a method and an apparatus for processing a nuclear energy spectrum. The apparatus includes: a detector, a nuclear pulse processing module, and a nuclear energy spectrum processing module; the detector is configured to detect nuclear radiation and convert the nuclear radiation into nuclear pulse signals with corresponding amplitudes; the nuclear pulse processing module is configured to shape the nuclear pulse signals into narrow pulses, and perform amplitude analysis on the narrow pulses to generate the nuclear energy spectrum; the nuclear energy spectrum processing module is configured to reduce a value of an energy resolution of the nuclear energy spectrum to obtain the nuclear energy spectrum with the energy resolution of the reduced value.

Water soluble, low alpha particle emission, electrically conductive coatings and techniques for formation thereof are provided. In one aspect, a method for forming an electrically-conductive coating on a substrate includes the steps of: forming an aqueous solution of a water soluble polymer (e.g., a polyvinylpyrrolidinone polymer or copolymer); adding electrically conductive filler particles to the aqueous solution above a percolation threshold to form a mixture; and depositing the mixture onto the substrate to form a low alpha particle emitting, electrically-conductive coating on the substrate, wherein the coating blocks alpha particles from being emitted from the substrate. An article and an alpha particle detector having a surface(s) thereof covered with the coating are also provided.

The active neutron spectrometer (1) comprises a polyhedral moderator body (2) of hydrogenated material having a first, a second and a third orthogonal main axis (X.sub.1, X.sub.2; Y.sub.1, Y.sub.2; Z.sub.1, Z.sub.2), a first series of thermal neutron detectors (3.sub.a1, 3.sub.a2, 3.sub.a3, 3.sub.a4, 3.sub.a5, 3.sub.a6, 3.sub.b1, 3.sub.b2, 3.sub.b3, 3.sub.b4, 3.sub.b5, 3.sub.b6) arranged along the first main axis (X.sub.1, X.sub.2), a second series of thermal neutron detectors (4.sub.a1, 4.sub.a2, 4.sub.a3, 4.sub.a4, 4.sub.a5, 4.sub.a6, 4.sub.b1, 4.sub.b2, 4.sub.b3, 4.sub.b4, 4.sub.b5, 4.sub.b6) arranged along the second main axis (Y.sub.1, Y.sub.2), and a third series of thermal neutron detectors (5.sub.a1, 5.sub.a2, 5.sub.a3, 5.sub.a4, 5.sub.a5, 5.sub.a6, 5.sub.b1, 5.sub.b2, 5.sub.b3, 5.sub.b4, 5.sub.b5, 5.sub.b6) arranged along the third main axis (Z.sub.1, Z.sub.2).

A method for evaluating a single-photon detector signal includes duplicating the single-photon detector signal into a first and a second signal. The first signal is processed and the second signal is either not processed or is processed in a manner different from the first signal. A differential signal is formed between the unprocessed or differently processed second signal and the processed first signal. The differential signal is evaluated to determine pulse events.

Systems and methods for high voltage conversion and multiplication for ionizing radiation detection are disclosed. According to an aspect, an electronic device comprises at least one detector configured for detecting ionizing radiation. Further, the electronic device comprises a translator assembly coupled to the at least one detector and configured to convert a voltage from a first voltage level to a second voltage level, wherein the at least one detector operates at the first voltage level. Further, the translator assembly is configured to voltage isolate the at least one detector operating at the first voltage level from a coupled electronic circuit operating at the second voltage level.