Embodiments of the present disclosure include a system for detecting neutrons with a housing, a gas chamber at least partially defined by the housing, an anode extending through at least a portion of the gas chamber, and a pseudogas arranged within the gas chamber. The pseudogas comprises a mixture of gas and suspended solid particles that contain an element with a high cross-section for thermal neutron capture.

A large-area X-ray gas detector includes a housing having an inner cavity and a ray entrance communicated with the inner cavity, a thin entrance window and a signal collection module. The inner cavity is filled with a working gas which is a non-electronegativity gas sensitive to the X-ray. The entrance window is hermetically connected to the ray entrance such that the X-ray enters into the inner cavity. The signal collection module comprises an anode wire electrode layer and a cathode electrode layer arranged parallel with each other in the inner cavity, in which the anode wire electrode layer has an anode wire for accessing to a high voltage, and the cathode electrode layer is grounded. The anode wire electrode layer collects electrons generated by the working gas under an action of the X-ray.

Boron nitride nanotubes (BNNTs) with 10B combined with a scintillation gas can serve as the basis for detecting thermal neutrons by detecting light from the decay products of the thermal neutron's absorption on the 10B atoms in the BNNT Material as the resultant decay products pass through the scintillating gas. BNNTs with 11B can be utilized as a scaffold for 238U and combined with a scintillation gas as the basis for detecting fast neutrons via detecting light from the fission decay products passing through the scintillating gas. Both technologies provide high spatial and temporal resolution for the detection of thermal neutrons and fast neutrons respectively.

Systems for landing and facilitating power flow or data transfer between an unmanned aerial vehicle (UAV) and a charging mat using a boom are described. The system includes a mat with a conductive mesh on the top and a conductive surface on the other bottom of the mat. The conductive mesh and bottom conductive surface are separated (electrically isolated) by an isolation core. The outer portion of the boom contacts part of the conductive mesh of the mat to create an electrical pathway. An inner portion of the boom penetrates through the top layer conductive mesh, through the isolating core, and contacts the bottom conductive surface of the mat to create another electrical pathway.

A large-area directional radiation detection system useful in detecting shielded radiological weapons may include a large number of prism-shaped detectors stacked in a two-dimensional array of particle detectors in which alternate detectors are displaced frontward and rearward in, for example, a checkerboard-type arrangement of detectors. If a source of radiation is in front of the array, the frontward detectors act as collimators for the rearward detectors, thereby producing a narrow detection peak among the rearward detectors. The lateral position of the detection peak indicates the lateral position of the source, and the width of the detection peak indicates the distance of the source from the detector array, thereby providing a three-dimensional determination of the source location. The high detection efficiency and large solid angle of the detector array enable rapid detection of even well-shielded threat sources at substantial distances, while simultaneously determining the positions of the detected sources.

Provided are a method for measuring dose distribution in a mixed radiation field of neutrons and gamma rays, and a method for measuring beam uniformity of a mixed radiation field of neutrons and gamma rays. The planar dose measuring method includes: a step of obtaining a total dose of neutrons and gamma rays by measuring with a dosimeter; and a step of analyzing a neutron dose. The method may effectively measure the doses of neutrons and gamma rays, may be applied to beam measurement and treatment plan validation, and thus improve the quality of treatment.

A fissile neutron detection system includes a neutron moderator and a neutron detector disposed proximate such that a majority of the surface area of the neutron moderator is disposed proximate the neutron detector. Fissile neutrons impinge upon and enter the neutron moderator where the energy level of the fissile neutron is reduced to that of a thermal neutron. The thermal neutron may exit the moderator in any direction. Maximizing the surface area of the neutron moderator that is proximate the neutron detector beneficially improves the reliability and accuracy of the fissile neutron detection system by increasing the percentage of thermal neutrons that exit the neutron moderator and enter the neutron detector.

A fissile neutron detection system includes an ionizing thermal neutron detector arrangement including an inner peripheral shape that at least substantially surrounds a moderator region for detecting thermal neutrons that exit the moderator region but is at least generally transparent to the incident fissile neutrons. A moderator is disposed within the moderator region having lateral extents such that any given dimension that bisects the lateral extents includes a length that is greater than any thickness of the moderator arrangement transverse to the lateral extents. The moderator can include major widthwise and major lengthwise lateral extents such that any given dimension across the lengthwise and widthwise lateral extents includes a length that is greater than any thickness of the moderator arrangement transverse to the lateral extents.

A device for detecting neutrons with an ionization chamber and with optical transduction includes a plurality of optical cavities, each cavity accommodating the free end of an optical fiber and having at least one inner wall coated at least partially with at least one active material. The optical cavities are filled with a gas that can be ionized by an ion arising from the reaction between a neutron and the active material. Each optical cavity is delimited by a cylinder that is closed at its longitudinal ends by a closing disk, the lateral inner wall of which is coated at least partially with an active material. The cylinders adjoin one another while being centered on the longitudinal axis. At least one of the cylinders is pierced laterally with an opening configured to allow through one of the optical fibers whose free end is accommodated in an adjacent cavity.

A fissile neutron detection system includes a neutron moderator and a neutron detector disposed proximate such that a majority of the surface area of the neutron moderator is disposed proximate the neutron detector. Fissile neutrons impinge upon and enter the neutron moderator where the energy level of the fissile neutron is reduced to that of a thermal neutron. The thermal neutron may exit the moderator in any direction. Maximizing the surface area of the neutron moderator that is proximate the neutron detector beneficially improves the reliability and accuracy of the fissile neutron detection system by increasing the percentage of thermal neutrons that exit the neutron moderator and enter the neutron detector.