A narrow thermal neutron detector includes a slidably receivable ionization thermal neutron detector module within an overall housing body. An active sheet layer of the ionization thermal neutron detector module can be tensioned across its width. The ionization thermal neutron detector module can include module upper major surface extents and module lower surface extents such that, when installed within the housing body, the module upper major surface extents are in a first spaced apart confronting relationship with housing upper major surface extents to define a first clearance and module lower major surface extents are in a second spaced apart confronting relationship with housing lower major surface extents to define a second clearance to accommodate housing flexing due to ambient pressure change. The housing body can be formed with a single opening for receiving the ionization thermal neutron detection module or with opposing first and second opposing end openings.

Compositions and methods for monitoring the quantity of actinides present in a test sample are disclosed. Compositions and methods for monitoring the motion of special nuclear materials through space are also described. Compositions and methods for monitoring the quantity of a fissile special nuclear material present in a test sample are disclosed. Compositions and methods for monitoring actinides during reprocessing of spent nuclear fuel after 30-year cool down are disclosed. Compositions and methods for monitoring actinides during reprocessing of spent nuclear fuel after 180 day cool down are also disclosed.

An apparatus and method for improving the sensitivity and energy response of neutron detectors and neutron dose rate meters. A beryllium layer is added to neutron detector moderators to improve the sensitivity of the detector. Energy dependence of the sensitivity is optimized by controlling the amount of beryllium in the moderator and by specifying the geometrical design parameters. The beryllium layer, in combination with additional material layers in the moderator, makes the detector response function correspond to the theoretical one in a wide range of energies. Response parameters of the neutron dose rate meter are within 20% of the theoretical response function in the neutron energy range from 500 keV to 10 GeV, and also in the energy range corresponding to thermal neutrons (about 1-100 meV).

A boron coated straw detector for use in a neutron detection system is disclosed comprising a boron coated straw having at least one boron-coated septum radially oriented and extending a pre-determined distance towards the center of the straw. Preferably, the straw comprises a plurality of septa comprising a rigid surface, coated on both sides with a boron composition. Preferably, the septa run the length of the straw detector from one end of the straw to the other. The area coated on the septa adds to the area coated on the arc segments offering a significant benefit in sensitivity of the neutron detector.

A .sup.3Helium gas counter comprising a container, a gas tube within the container, and a mixture of .sup.3Helium and Xenon or a mixture of .sup.3Helium and Krypton. A method of making a .sup.3Helium gas counter comprising providing a container, placing a gas tube within the container, and depositing a mixture of .sup.3Helium and Xenon or a mixture of .sup.3Helium and Krypton into the gas tube.

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.

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 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. BN-NTs 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.

To address the shortcomings presented in the prior art, the present invention provides a system and method to provide improved irrigation management through the detection of fast neutrons. According to a preferred embodiment, the fast neutron detector of the present invention includes a 4-He based noble gas detector, a power source, a signal processing circuit, and a resistor in series with a preamplifier and a shaping amplifier to produce a processed signal. According to a further preferred embodiment, the present invention preferably further includes a signal channel analyzer and a pulse counter/rate meter. According to a further preferred embodiment, the present invention includes a controller which receives a count of detected fast neutrons and translates the detected number of fast neutrons into an irrigation map indicating the required levels of irrigation needed for selected areas of a given field based on the detected moisture levels.