Abstract: A neutron detection system includes a neutron scintillator having a thickness greater than an optimal thickness and less than twice the optimal thickness. The system includes a first layer of wavelength shifting fiber optic elements positioned on a first side of the neutron scintillator. Adjacent fibers of the first layer pass light to distinct photo-multiplication devices. The system further includes a second layer of wavelength shifting fiber optic elements positioned on a second side of the neutron scintillator. Adjacent fibers of the second layer pass light to distinct photo-multiplication devices. The two layers may share photo-multiplication devices or use different sets of photo-multiplication devices. The system includes a controller that distinguishes a neutron radiation event from a gamma radiation event in response to electronic signals from the distinct photo-multiplication devices.

Abstract: A radiation detector system/method implementing a corrected energy response detector is disclosed. The system incorporates charged (typically tungsten impregnated) injection molded plastic that may be formed into arbitrary detector configurations to affect radiation detection and dose rate functionality at a drastically reduced cost compared to the prior art, while simultaneously permitting the radiation detectors to compensate for radiation intensity and provide accurate radiation dose rate measurements. Various preferred system embodiments include configurations in which the energy response of the detector is nominally isotropic, allowing the detector to be utilized within a wide range of application orientations. The method incorporates utilization of a radiation detector so configured to compensate for radiation counts and generate accurate radiation dosing rate measurements.

Abstract: A radiation detector dosimeter system/method implementing a corrected energy response detector is disclosed. The system incorporates charged (typically tungsten impregnated) injection molded plastic that may be formed into arbitrary detector configurations to affect radiation detection and dose rate functionality at a drastically reduced cost compared to the prior art, while simultaneously permitting the radiation detectors to compensate for radiation intensity and provide accurate radiation dose rate measurements. Various preferred system embodiments include configurations in which the energy response of the detector is nominally isotropic, allowing the detector to be utilized within a wide range of application orientations. The method incorporates utilization of a radiation detector so configured to compensate for radiation counts and generate accurate radiation dosing rate measurements.

Abstract: A mixed organic crystal according to one embodiment includes a single mixed crystal having two compounds with different bandgap energies, the organic crystal having a physical property of exhibiting a signal response signature for neutrons from a radioactive source, wherein the signal response signature does not include a significantly-delayed luminescence characteristic of neutrons interacting with the organic crystal relative to a luminescence characteristic of gamma rays interacting with the organic crystal. According to one embodiment, an organic crystal includes bibenzyl and stilbene or a stilbene derivative, the organic crystal having a physical property of exhibiting a signal response signature for neutrons from a radioactive source.

Abstract: Methods and apparatus for a detector system to detect gamma and neutron radiation. In one embodiment, a detector comprises a tank to hold a liquid, a plurality of tubes adjacent the tank to detect neutrons, and a plurality of photon detectors to detect Cherenkov light generated by gamma radiation in the liquid. The tank is configured to contain the liquid so that the liquid generates the Cherenkov light and moderates the neutrons.

Abstract: A system of the present invention is capable of detecting, imaging and measuring both neutrons and gamma rays. The system has three parallel plates each containing a plurality of detectors. Each plate has different detectors. The first plate has plastic scintillation detectors. The second plate has a plurality of stilbene scintillation detectors having pulse-shape discrimination (PSD) properties. The third plate has a plurality of inorganic detectors. The first plate and the second plate are used in connection to detect, image and measure neutrons. The second plate and the third plate are used in connection to detect, image, and measure gamma rays.

Abstract: A neutron detection apparatus can include a scintillator having a formula of Gd3(1-x)Y3aAl5(1-y)Ga5yO12. In an embodiment, x is at least approximately 0.05 and no greater than approximately 0.5 and y is at least approximately 0.05 and no greater than approximately 0.95. The scintillator can be capable of emitting scintillating light in response to interactions with neutrons. The neutron detection apparatus can also include a photosensor optically coupled to the scintillator.

Abstract: A method for detecting particles is presented. The method comprises generating a reaction to a plurality of particles using a converter material, wherein the converter material is operable to interact with the plurality of particles. Further, the method comprises converting a response to the reaction to a readable electrical signal using a sensor, wherein the sensor comprises an array of discrete pixels. Also, the method comprises processing the readable electrical signal from the sensor to generate information for each pixel on the array of discrete pixels and transmitting the information to a processing unit. Furthermore, the method comprises analyzing the information using the processing unit to determine instances of impingement of the plurality of particles on said array of discrete pixels. Finally, the method comprises an aggregate of sensors that function in parallel to result in a highly sensitive particle detection system.

Abstract: A fast neutron imaging apparatus and method of constructing fast neutron radiography images, the apparatus including a neutron source and a detector that provides event-by-event acquisition of position and energy deposition, and optionally timing and pulse shape for each individual neutron event detected by the detector. The method for constructing fast neutron radiography images utilizes the apparatus of the invention.

Abstract: [Problems to be Solved] A neutron scintillator excellent in neutron detection efficiency and n/? discrimination ability, and a neutron detector using the neutron scintillator are provided. [Means to Solve the Problems] A neutron scintillator comprising a eutectic body composed of laminar lithium fluoride crystals and laminar calcium fluoride crystals alternately arranged in layers, the thickness of the lithium fluoride crystal layers in the eutectic body being 0.1 to 5 ?m; or a neutron scintillator comprising a eutectic body composed of laminar lithium fluoride crystals and laminar calcium fluoride crystals alternately arranged in layers, the calcium fluoride crystal layers in the eutectic body being linearly continuous in at least one direction; and a neutron detector basically constructed from any of the neutron scintillators and a photodetector.

Abstract: A scintillator device includes a polymeric polymer matrix, a neutron sensing particulate material dispersed within the polymer matrix, and a scintillating particulate material dispersed within the polymer matrix. In an embodiment, the neutron sensing particulate material has an average characteristic length of not greater than about 3 microns. The scintillating particulate material has an average characteristic length of at least about 16 microns. In another embodiment, a ratio of the average characteristic length of the scintillating particulate material to the average characteristic length of the neutron sensing particulate material is at least about 55. In a further embodiment, an energy deposited in the scintillating particulate material by a positively charged particle is at least about 1.25 MeV.

Abstract: A neutron detection system comprising a radiation portal monitor is disclosed. The radiation portal monitor includes a neutron moderator sheet and a neutron-sensing panel and is configured to receive incoming neutrons through a neutron collection portal area. The neutron-sensing panel comprises a neutron-sensing material optically coupled to a plurality of optical fibers such that the neutron moderator sheet and the neutron-sensing panel are disposed substantially parallel to the neutron collection portal area.

Abstract: The direction of the main axis of a bearing is adjusted by turning a supporting base (12a) that is supporting the bearing, and by then receiving a neutron beam that has been transmitted through the bearing from the direction of the main axis thereof, and converting it into an electromagnetic wave, and by then forming images using the received electromagnetic wave, lubricant distribution data that shows the distribution of a lubricant inside the bearing is acquired.

Abstract: In this lubricant distribution acquisition device (1), neutron beams (L1) that have been transmitted through a bearing (X) from the direction of the main axis thereof or from an oblique direction relative to the main axis thereof are converted into electromagnetic waves, and, by forming images using the received electromagnetic waves, lubricant distribution data that shows the distribution of a lubricant inside the bearing is acquired. As a result, it is possible to ascertain in detail the behavior of the lubricant inside the bearing without dismantling the bearing.

Abstract: A system for efficient neutron detection is described. The system includes a neutron scintillator formed with a number of protruding parallel ribs each side of the scintillator, forming a first set of ribs and a second set of ribs. The ribs have a protrusion height that provides a selected neutron absorption efficiency. The system includes a set of wavelength shifting fibers positioned between each adjacent pair of ribs on both the first side and the second side. Each set of wavelength shifting fibers are in optical proximity to the adjacent pair of the ribs that set of fibers are positioned between.

Abstract: Scintillator compositions are provided which include a solvent or matrix containing a fluorophore having the formula (I) and/or a fluorophore having the formula (II), wherein R1 and R2, being identical or different, are independently chosen from the group consisting of hydrogen, halogen, alkyl which optionally contains one or more heteroatoms, alkoxy, aryl and alkyne with an aryl end group; R3 is chosen from the group consisting of hydrogen, alkyl which optionally contains one or more heteroatoms, aryl, heterocycle, ether and ester; R4 and R5, being identical or different, are independently chosen from the group consisting of hydrogen, alkyl which optionally contains one or more heteroatoms, aryl, heterocycle, ether and ester, whereby the R4 and R5 groups are optionally combined to one cyclic structure; and R6, if present, is chosen from the group consisting of hydrogen, aryl and alkyl.

Abstract: A method is provided to detect neutrons using a boron-shielded gamma-ray detector, which will detect the 0.48-MeV prompt gamma ray due to the 10B (n,?)7Li reaction. The gamma ray detector can be a proportional gas counter, a scintillation based detector, or a semiconductor detector. Monoenergetic prompt gammas will produce a sharp peak in the pulse height spectrum of a gamma-ray spectroscopy detector. By surrounding a gamma detector with a layer containing 10B, we can measure the gamma signal and neutron signal at the same time and at the same physical location in an instrument. The approach can be used to measure neutron porosity simultaneous with gamma-ray counting or spectroscopy at the same location as long as the 0.48-keV gamma-ray from the neutron reaction does not interfere with the gamma-ray measurement.

Abstract: Provided is a scintillation neutron detector capable of measuring neutrons with precision even under a high amount of ? rays as background noise and excellent in neutron counting precision, the scintillation neutron detector comprising a neutron scintillator crystal containing 6Li, and the crystal having a specific surface area of no less than 60 cm2/cm3.

Abstract: Methods and apparatus for a detector system to detect gamma and neutron radiation. In one embodiment, a detector comprises a tank to hold a liquid, a plurality of tubes adjacent the tank to detect neutrons, and a plurality of photon detectors to detect Cherenkov light generated by gamma radiation in the liquid. The tank is configured to contain the liquid so that the liquid generates the Cherenkov light and moderates the neutrons.

Abstract: A fabrication method is provided for making a high efficiency neutron detector using a scintillator medium coupled with fiber optic light guides. The light guides provide light pulses to photo sensor and thereby to high speed analog to digital conversion and digital electronics that perform digital pulse shape discrimination for near zero gamma cross talk.

Abstract: A thermal neutron monitor includes at least one neutron scintillator sheet interposed between light guides. Scintillation light emitted in opposite transverse directions is captured by the light guides and conveyed to a common detector. The sandwiched geometry of the monitor avoids the need to provide multiple detectors and permits construction of a relatively inexpensive, compact monitor.

Abstract: Disclosed is an apparatus for detecting a neutron. The apparatus includes: a neutron interaction material configured to emit a charged particle upon absorbing a neutron; a plurality of nanoparticles distributed in the neutron interaction material, each nanoparticle in the plurality being configured to scintillate upon interacting with the charged particle to emit a pulse of light; a photodetector coupled to the neutron interaction material and configured to receive the pulse of light and generate a signal based on the received pulse of light; and a processor configured to receive the signal in order to detect the neutron.

Abstract: Disclosed is an apparatus for detecting neutrons. The apparatus includes a plurality of neutron detector cells, each detector cell comprising a cathode surrounding an anode wherein the cathode of each cell is common to an adjacent detector cell. A neutron interaction material covers an interior surface of the cathode in each neutron detector cell, the neutron interaction material being configured to emit a charged particle between the cathode and the anode upon interacting with a neutron.

Abstract: [Problems to be Solved] A neutron scintillator excellent in neutron detection efficiency and n/? discrimination ability, and a neutron detector using the neutron scintillator are provided. [Means to Solve the Problems] A neutron scintillator comprising a eutectic body composed of laminar lithium fluoride crystals and laminar calcium fluoride crystals alternately arranged in layers, the thickness of the lithium fluoride crystal layers in the eutectic body being 0.1 to 5 ?m; or a neutron scintillator comprising a eutectic body composed of laminar lithium fluoride crystals and laminar calcium fluoride crystals alternately arranged in layers, the calcium fluoride crystal layers in the eutectic body being linearly continuous in at least one direction; and a neutron detector basically constructed from any of the neutron scintillators and a photodetector.

Abstract: A detector (100) for detecting neutrons comprises a neutron reactive material (102) adapted to interact with neutrons to be detected and release ionizing radiation reaction products in relation to said interactions with neutrons. The detector also comprises a first semiconductor element (101) being coupled with said neutron reactive material (102) and adapted to interact with said ionizing radiation reaction products and provide electrical charges proportional to the energy of said ionizing radiation reaction products. In addition electrodes are arranged in connection with said first semiconductor element (101) for providing charge collecting areas (106) for collecting the electrical charges and to provide electrically readable signal proportional to said collected electrical charges. The thickness of the first semiconductor element (101) is adapted to be electrically and/or physically so thin that it is essentially/practically transparent for incident photons, such as background gamma photons.

Abstract: A thermal neutron detector and method employ Gd-containing nanoscintillators. Thermal neutron radiation is detected by observing scintillation events from the nanoscintillators.

Abstract: The present disclosure provides a protective scintillator package for enclosing a scintillator wherein at least one component in the package is at least partially formed from a viscoelastic material. The protective package may comprise both elastic and viscoelastic materials, which may both be included in one component or may be in differing components. The present disclosure further provides radiation detectors using such scintillator packages, as well as logging tools, and methods for oil exploration.

Abstract: The present invention provides a detection element that can suppress generation of a residual image. A sensor portion includes a semiconductor layer, an upper electrode and a lower electrode. The semiconductor layer generates charges due to light being illuminated thereto. The upper electrode applies a bias voltage to the semiconductor layer. The lower electrode collects charges that have been generated at the semiconductor layer. The charges that have been generated at the semiconductor layer are collected and accumulated by the lower electrode. In the detection element, a saturation prevention circuit (diode and second bias line) is provided through which the accumulated charges flow-out when the charges that have been generated at the semiconductor layer are collected and a voltage level of the lower electrode becomes a saturation prevention voltage level Vs.

Abstract: Disclosed below are representative embodiments of methods, apparatus, and systems for detecting particles, such as radiation or charged particles. One exemplary embodiment disclosed herein is particle detector comprising an optical fiber with a first end and second end opposite the first end. The optical fiber of this embodiment further comprises a doped region at the first end and a non-doped region adjacent to the doped region. The doped region of the optical fiber is configured to scintillate upon interaction with a target particle, thereby generating one or more photons that propagate through the optical fiber and to the second end. Embodiments of the disclosed technology can be used in a variety of applications, including associated particle imaging and cold neutron scattering.

Abstract: A fabrication method is provided for making a high efficiency neutron detector using a scintillator medium coupled with fiber optic light guides. The light guides provide light pulses to photo sensor and thereby to high speed analog to digital conversion and digital electronics that perform digital pulse shape discrimination for near zero gamma cross talk. Optionally, microwave curing techniques are used for fabricating a high performance neutron detector with high reliability and homogenous distribution of the particles encapsulated in a polymer to produce a high performance neutron detector.

Abstract: A method used to yield irradiation product with minimal impurity for the solid target for gallium (Ga)-68/germanium (Ge)-68 generator mainly consists of the procedures: first calculate the thickness d for the electroplated gallium (Ga)-69 on the solid target; and then through a graph of decay curves including 69Ga(p, 2n) 68Ge target thickness and incident energy with 5 different incident energy doses, derive the corresponding irradiation energy dose Yi for each group after decay; and through the graph including 69Ga(p,2n)68Ge incident energy and reaction cross-sectional area, derive the nuclear reaction cross-sectional area for each group for germanium(Ge)-68, gallium (Ga)-68, zinc (Zn)-65 and figure out the mean reaction area (MRA) from the reaction cross-sectional area of each group; and select the maximum germanium(Ge)-68 MRA value and the minimum gallium (Ga)-68 and zinc (Zn)-65 MRA values; and generate the required default irradiation energy for the MRA of each group.

Abstract: An instrument that will directly image the fast fission neutrons from a special nuclear material source wherein the neutron detection efficiency is increased has been described. Instead of the previous technique that uses a time-of-flight (TOF) between 2 widely spaced fixed planes of detectors to measure scatter neutron kinetic energy, we now use the recoil proton energy deposited in the second of the 2 scatter planes which can now be repositioned much closer together. Allowing the 2 planes to be placed closer together has been shown to provide up to about a ˜170% improvement in detection efficiency without adding additional detectors and ancillary electronics. The distance between planes also may be dynamically changed using a suitable common technique such as a gear- or motor-drive to toggle between the various positions.

Abstract: There is provided a high-sensitivity organic semiconductor radiation/light sensor and a radiation/light detector which can detect rays in real time. In the high-sensitivity organic semiconductor radiation/light sensor, a signal amplification wire 2 is embedded in an organic semiconductor 1. Carriers created by passage of radiation or light are avalanche-amplified by a high electric field generated near the signal amplification wire 2 by means of applying a high voltage to the signal amplification wire 2, thus dramatically improving detection efficiency of rays. Hence, even rays exhibiting low energy loss capability can be detected in real time with high sensitivity.

Abstract: A method according to one embodiment includes growing an organic crystal from solution, the organic crystal exhibiting a signal response signature for neutrons from a radioactive source. A system according to one embodiment includes an organic crystal having physical characteristics of formation from solution, the organic crystal exhibiting a signal response signature for neutrons from a radioactive source; and a photodetector for detecting the signal response of the organic crystal. A method according to another embodiment includes growing an organic crystal from solution, the organic crystal being large enough to exhibit a detectable signal response signature for neutrons from a radioactive source.

Abstract: A neutron detector includes a coincidence detector to detect coincidence events in which each coincidence event indicates proximity in time of a first signal and a second signal. The first signal indicates detection of at least one of a neutron or a gamma ray, and the second signal indicates detection of a gamma ray by a gamma ray detector. A data processor identifies detection of neutron radiation based on characteristics of an energy spectrum of the gamma rays associated with the second signals that correspond to the coincidence signals.

Abstract: A radiation detection system can include a photo sensor to receive light from a scintillator via an input and to send an electrical pulse at an output in response to receiving the light. The radiation detection system can also include a pulse analyzer that can determine whether the electrical pulse corresponds to a neutron-induced pulse, based on a ratio of an integral of a particular portion of the electrical pulse to an integral of a combination of a decay portion and a rise portion of the electrical pulse. Each of the integrals can be integrated over time. In a particular embodiment, the pulse analyzer can be configured to compare the ratio with a predetermined value and to identify the electrical pulse as a neutron-induced pulse when the ratio is at least the predetermined value.

Abstract: The invention is directed to a liquid scintillating composition containing (i) one or more non-polar organic solvents; (ii) (lithium-6)-containing nanoparticles having a size of up to 10 nm and surface-capped by hydrophobic molecules; and (iii) one or more fluorophores. The invention is also directed to a liquid scintillator containing the above composition.

Abstract: A system for efficient neutron detection is described. The system includes a neutron scintillator formed with a number of protruding parallel ribs each side of the scintillator, forming a first set of ribs and a second set of ribs. The ribs have a protrusion height that provides a selected neutron absorption efficiency. The system includes a set of wavelength shifting fibers positioned between each adjacent pair of ribs on both the first side and the second side. Each set of wavelength shifting fibers are in optical proximity to the adjacent pair of the ribs that set of fibers are positioned between.

Abstract: A neutron detector employs a porous material layer including pores between nanoparticles. The composition of the nanoparticles is selected to cause emission of electrons upon detection of a neutron. The nanoparticles have a maximum dimension that is in the range from 0.1 micron to 1 millimeter, and can be sintered with pores thereamongst. A passing radiation generates electrons at one or more nanoparticles, some of which are scattered into a pore and directed toward a direction opposite to the applied electrical field. These electrons travel through the pore and collide with additional nanoparticles, which generate more electrons. The electrons are amplified in a cascade reaction that occurs along the pores behind the initial detection point. An electron amplification device may be placed behind the porous material layer to further amplify the electrons exiting the porous material layer.

Abstract: A neutron detection system includes a neutron scintillator having a thickness greater than an optimal thickness and less than twice the optimal thickness. The system includes a first layer of wavelength shifting fiber optic elements positioned on a first side of the neutron scintillator. Adjacent fibers of the first layer pass light to distinct photo-multiplication devices. The system further includes a second layer of wavelength shifting fiber optic elements positioned on a second side of the neutron scintillator. Adjacent fibers of the second layer pass light to distinct photo-multiplication devices. The two layers may share photo-multiplication devices or use different sets of photo-multiplication devices. The system includes a controller that distinguishes a neutron radiation event from a gamma radiation event in response to electronic signals from the distinct photo-multiplication devices.

Abstract: A neutron detector employs a porous material layer including pores between nanoparticles. The composition of the nanoparticles is selected to cause emission of electrons upon detection of a neutron. The nanoparticles have a maximum dimension that is in the range from 0.1 micron to 1 millimeter, and can be sintered with pores thereamongst. A passing radiation generates electrons at one or more nanoparticles, some of which are scattered into a pore and directed toward a direction opposite to the applied electrical field. These electrons travel through the pore and collide with additional nanoparticles, which generate more electrons. The electrons are amplified in a cascade reaction that occurs along the pores behind the initial detection point. An electron amplification device may be placed behind the porous material layer to further amplify the electrons exiting the porous material layer.

Abstract: The solid scintillator according to the present invention is expressed by the following formula (1): [Formula 1] (M1-x-yGdxCey)3J5O12??(1) (wherein M is at least one element of La and Tb; J is at least one metal selected from the group consisting of Al, Ga, and In; and x and y are such that 0.5?x?1 and 0.000001?y?0.2). The transmittance of light having a wavelength of 550 nm measured at a thickness of 2 mm is equal to or greater than 40%. The solid scintillator according to the present invention can be manufactured at low cost, has a high light emitting power, and does not release Cd because Cd is not contained.

Abstract: A simple method is developed for detection of fast neutrons for systems of detection of radioactive materials, which does not involve moderator systems, operates on the real time scale and ensures high detection efficiency. The method includes conversion of the cascade of gamma-quanta formed as a result of inelastic scattering of neutrons in a converter material with high atomic number into a set of light scintillations by a scintillator, processing of signals obtained in recording of said scintillations, formation of counting pulses with frequency proportional to the neutron flux and their recording according to an appropriate algorithm. Inorganic scintillators with high effective atomic number are used, and, as converter materials for inelastic scattering of neutrons, materials with high atomic numbers are used, which are a constituent part of said inorganic scintillators.

Abstract: A scintillator for neutron detection, comprising a metal fluoride crystal containing, as constituent elements, a metal having a valence of 2 or higher, such as calcium, aluminum or yttrium; lithium; and fluorine, the metal fluoride crystal containing 1.1 to 20 atoms per unit volume (atoms/nm3) of 6Li, having an effective atomic number of 10 to 40, containing a lanthanoid such as cerium, praseodymium or europium, and being represented by, for instance, LiCaAlF6, LiSrAlF6 and LiYF4. The scintillator for neutron detection has high sensitivity to neutron rays, and is reduced in a background noise attributed to ? rays.

Abstract: Dual modality detection devices and methods are provided for detecting nuclear material, the devices include a neutron detector including multiple neutron detection modules; and a gamma detector including multiple gamma detection modules, where the multiple neutron detection modules and the multiple gamma detection modules are integrated together in a single unit to detect simultaneously both gamma rays and neutrons.

Abstract: There are provided an apparatus capable of complying with arbitrary data acquisition period (frame rate) change instruction without increasing load and cost, and a method and a system for controlling such an apparatus. To realize this, in the present invention, there are included an area sensor for reading out an electric signal accumulated in a plurality of pixels arranged in a matrix, line by line, and a control unit for controlling the area sensor. The area sensor operates in a first operation for deriving radiation image data by reading during irradiation with radiation, and a second operation for deriving the radiation image data by reading during non-irradiation with radiation, alternately. The control unit switches a period for deriving the radiation image data during a time period from an end of the reading in the first operation until an end of the reading in the second operation.

Abstract: A neutron detection system comprising a radiation portal monitor is disclosed. The radiation portal monitor includes a neutron moderator sheet and a neutron-sensing panel and is configured to receive incoming neutrons through a neutron collection portal area. The neutron-sensing panel comprises a neutron-sensing material optically coupled to a plurality of optical fibers such that the neutron moderator sheet and the neutron-sensing panel are disposed substantially parallel to the neutron collection portal area.

Abstract: A scintillating material Cs(2-z)RbzLiLn(1-x)X6:xCe3+, where X is either Br or I, Ln is Y or Gd or Lu or Sc or La, where z is greater or equal to 0 and less or equal to 2, and x is above 0.0005 useful for detecting neutrons in a sample of radiation.

Abstract: A directional neutron detector consisting of very thin plastic scintillation fibers and optically coupled to a photo-sensor array, where the directionality of Neutrons is estimated from the sequence of fibers traversed by the scattered protons and energy deposited in each one of them. Several fabrication methods of the large thin fiber arrays are described.

Abstract: To provide a scintillator for neutron detection which has high sensitivity to neutron rays, and is reduced in a background noise attributed to ? rays. [Means to Solve the Problems] A scintillator for neutron detection, comprising a metal fluoride crystal containing, as constituent elements, a metal having a valence of 2 or higher, such as calcium, aluminum or yttrium; lithium; and fluorine, the metal fluoride crystal containing 1.1 to 20 atoms per unit volume (atoms/nm3) of 6Li, having an effective atomic number of 10 to 40, containing a lanthanoid such as cerium, praseodymium or europium, and being represented by LiCaAlF6, LiSrAlF6, LiYF4 etc.