Abstract:
Die Erfindung betrifft ein Dosimeter (1, 8) zur Erfassung polyenergetischer Neutronenstrahlung. Vorgesehen sind ein Aufnahmebereich (6) für zumindest ein Detektionselement (7) und zumindest ein Neutronenabsorptionsbereich (2, 3). Der Neutronenabsorptionsbereich (2, 3) besteht aus einem chlorhaltigen Material, bei dem Chlor einen atomaren Bestandteil eines Material-Moleküls darstellt.
Abstract:
A neutron spectrometer is disclosed, which consists of a Helium-3 proportional counter connected by cable to signal and data processing circuits, and a series of moderator shells and moderator lids. The series of cylindrical moderator shells are designed to fit within one another, like Russian Matryoshka dolls, with the counter at the center. Small air gaps are introduced between the shells so that removal of one shell from another is facilitated. The counter is placed within the smallest cylindrical moderator shell, and then a circular lid matching the smallest shell is placed on the opening of the first shell to close the first shell. This first closed shell is then placed within a second shell, which shell is closed with its corresponding circular lid. The cable is routed through the series of shells. A method for using the invention is also disclosed, wherein the counter reading is taken from the fully-assembled neutron spectrometer. Then the outer cylindrical shell and circular lid pair is removed, and another measurement of the counter is recorded. This is continued until the last shell is removed, and a measurement is recorded using the bare counter.
Abstract:
A method for detecting a neutron includes providing a first voltage to an input electrode of a microchannel plate, providing a second voltage to an output electrode of the microchannel plate, the second voltage being more positive than the first voltage, measuring a signal on the output electrode, and detecting a neutron based on a comparison of the signal at the output electrode with a baseline value.
Abstract:
The present invention includes a method for radiation detection. The present invention utilized boron-coated detectors as a new alternative to large 3He tubes that will address the timing limitations of 3He-based detectors in active interrogation systems, by providing a 100-times faster ion collection time. This may enable the counting of prompt neutrons starting within 10 μs following each gamma ray pulse. Current 3He-based detectors can only count delayed neutrons, and the linac pulse rate is severely limited by the lengthy times required to count these very late neutrons. If detection of the prompt component can be achieved, up to 150 times more neutrons can be detected in each pulse and pulse rate can be increased by more than 10 fold, giving a net sensitivity gain of 1500 while using the same detection array and linac.
Abstract:
The present invention discloses a boron-coated neutron detector, comprising a cathode tube with a plurality of passages formed therein along its longitudinal direction, the inner wall of each passage being coated with boron material; an electrode wire serving as an anode and arranged longitudinally in each of the passages, the electrode wire adapted to be applied with high voltage; and an insulating end plate to which each end of the cathode tube is fixed, the electrode wire being fixed to the cathode tube via the insulating end plate. Preferably, the cathode tube is formed by jointing a plurality of boron-coated substrates. By arranging in the cathode tube a plurality of passages coated with boron material on their inner walls, the boron-coated neutron detector increases the detection efficiency of the neutron detector, which may reach or even exceed the detection efficiency of the 3 He neutron detector of the same size, and the cost thereof is much cheaper than the 3 He neutron detector.
Abstract:
The invention relates to a method for measuring the number of strikes of high-energy neutrons in a predetermined detection volume. The aim of determining the flow of high-energy neutrons is achieved by a method comprising the following steps: provision of a neutron detector (1) comprising a moderator device (2), which is composed of a material containing carbon and a counting tube (4) that is filled with counting gas, said counting tube (4) being configured to detect neutrons; a measurement is carried out, during which the number of events that occur in the counting tube (4) are determined as temporal functions; a start time (S1, S2, S3) is defined; an evaluation time window (f1) is defined after the start time; the events that have been measured in the evaluation time window (f1) are evaluated and a counter value is output, said value being dependent on the number of strikes of high-energy neutrons in the detector at the start time (S1, S2, S3) and on the result of the evaluation.
Abstract:
The invention relates to a method for determining the spectral and spatial distribution of a braking photon flow along at least one direction in space (x, y, z), characterised in that the method comprises measuring the neutrons resulting from the impact of the braking photons (ph) on at least one conversion target (5) which is moved in the direction (x, y, z) in space. The invention can be used for X-rays, medical imaging, tomography, etc.