Abstract: 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.

Abstract: A detector arrangement (10) for the detection of ionizing radiation comprises at least one light sensing device (14) and a multifunctional coating (12) arranged in an interacting relation to said at least one light sensing device (14), whereby said multifunctional coating (12) is configured to perform the functions of reflecting light of a given wavelength; and converting at least part of thermal and/or epi-thermal neutrons entering said multifunctional coating (12) into light (15).

Abstract: The present disclosure includes a radiological material detector having a convertor material that emits one or more photons in response to a capture of a neutron emitted by a radiological material; a photon detector arranged around the convertor material and that produces an electrical signal in response to a receipt of a photon; and a processor connected to the photon detector, the processor configured to determine the presence of a radiological material in response to a predetermined signature of the electrical signal produced at the photon detector. One or more detectors described herein can be integrated into a detection system that is suited for use in port monitoring, treaty compliance, and radiological material management activities.

Abstract: A method for providing a boron-lined neutron detector. The method includes providing a boron-containing material and providing water. The method includes mixing the boron-containing material into the water to create a water-based liquid mixture and providing a substrate of a cathode of the neutron detector. The method includes applying the water-based liquid mixture to the substrate of the cathode and removing water from the water-based liquid applied to the substrate to leave a boron-containing layer upon the substrate that is sensitive to neutron impingement. The step of providing a boron-containing material may be to provide the material to include B-10.

Abstract: A neutron detector that includes an anode and a cathode. The cathode includes at least one portion that has a porous substrate with surface segments that define open pores and a layer of neutron sensitive material on the surface segments of the porous substrate.

Abstract: A boron carbide solid state neutron detector and method of using the detector is disclosed, wherein the detector includes a layer of boron carbide wherein the boron carbide layer is an electrically active part of the detection device, a sensing mechanism inherent to said boron carbide layer, wherein the sensing mechanism detects changes in the boron carbide layer caused by the interception of neutrons and a monitoring device coupled to the sensing mechanics.

Abstract: An apparatus and method for detecting neutrons, particularly, with directional sensitivity. The apparatus is a detector with a scintillator containing high neutron-capture-cross-section atoms for capturing neutrons and emitting electromagnetic radiation, and an optical detector for detecting the emitted electromagnetic radiation and for generating an electrical signal. The high neutron-capture-cross-section atoms may be gadolynium, in particular, and the detector may additionally have a moderator for converting fast neutrons into thermal neutrons that are then captured by the high neutron-capture-cross-section atoms.

Abstract: A neutron rem meter utilizing proton recoil and thermal neutron scintillators to provide neutron detection and dose measurement. In using both fast scintillators and a thermal neutron scintillator the meter provides a wide range of sensitivity, uniform directional response, and uniform dose response. The scintillators output light to a photomultiplier tube that produces an electrical signal to an external neutron counter.

Abstract: This invention relates to a method and apparatus for improving the precision of at least one of neutron coincidence counting and neutron multiplicity counting. The method includes the steps of: (1) sampling the real and accidental coincident pulses at the incoming pulse rate; and (b) sampling the accidental coincidences at a clock rate, wherein the clock rate is much faster than the pulse rate. The clock rate is faster than the pulse rate by a factor of 5 to 10 (in the preferred embodiment, approximately 4 MHz).

Abstract: A neutron detector array is capable of measuring a wide range of neutron fluxes. The array includes multiple semiconductor neutron detectors. Each detector has a semiconductor active region that is resistant to radiation damage. In one embodiment, the array preferably has a relatively small size, making it possible to place the array in confined locations. The ability of the array to detect a wide range of neutron fluxes is highly advantageous for many applications such as detecting neutron flux during start up, ramp up and full power of nuclear reactors.

Abstract: A neutron detection device is housed in a metal enclosure containing a first detector with a high-sensitivity fission chamber, and a second detector having a low-sensitivity fission chamber and a boron-lined ionization chamber compensated for gamma radiation. The detection device is useful for extended range measurement of the neutron fluence rate outside the core of a nuclear reactor.

Abstract: A high-efficiency apparatus for detecting fast neutrons includes an assembly of disks of solid state charged particle detector material, or other appropriate charged particle detecting devices, disposed between adjacent thick (on the order of 1 mm) disks of fissionable material. The fissionable material must be an isotope that has a sharp increase in the neutron-induced fission cross section at a neutron energy of about 100 keV or greater, i.e., a fast neutron. An array of such assemblies housed in a thermal neutron shielding structure provides a threshold detector for fast neutrons resulting from neutron-induced fission of the fissionable material.

Abstract: An improved thermal neutron flux detector and measuring apparatus of the neutron induced transmutation type. The disclosed apparatus employs a plastic film electret and a fissionable material such as uranium-235 for generating energetic ion fission fragments-fragments which alter the electric potential of the electret in a measurable manner. Electret characteristics and fissionable material member fabrication are also disclosed along with uses of the instrument for dosimetry and other purposes.