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 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 scintillator system is provided to detect the presence of fissile material and radioactive material. One or more neutron detectors include scintillator material, and are optically coupled to one or more wavelength shifting fiber optic light guide media that extend from the scintillator material to guide light from the scintillator material to a photosensor. An electrical output of the photosensor is connected to an input of a pre-amp circuit designed to provide an optimum pulse shape for each of neutron pulses and gamma pulses in the detector signals. Scintillator material as neutron detector elements can be spatially distributed with interposed moderator material. Individual neutron detectors can be spatially distributed with interposed moderator material. Detectors and moderators can be arranged in a V-shape or a corrugated configuration.

Abstract: A system, method, and mobile frame structure detect radiation and identify materials associated with radiation that has been detected. A mobile frame structure is maneuvered over an entity to be examined. A set of radiation data associated with the entity is received from a set of radiation sensors that are mechanically coupled to the at least one portion of the mobile frame structure. At least one histogram is generated based on the set of radiation data. The at least one histogram is compared to multiple spectral images associated with known materials. The at least one histogram is determined to substantially match at least one of the multiple spectral images. A determination is made whether a material associated with the at least one of the multiple spectral images is a hazardous material. Personnel is notified that the at least one radiation source is a hazardous material.

Abstract: A system, method, and mobile frame structure detect radiation and identify materials associated with radiation that has been detected. A mobile frame structure is maneuvered over an entity to be examined. A set of radiation data associated with the entity is received from a set of radiation sensors that are mechanically coupled to the at least one portion of the mobile frame structure. At least one histogram is generated based on the set of radiation data. The at least one histogram is compared to multiple spectral images associated with known materials. The at least one histogram is determined to substantially match at least one of the multiple spectral images. A determination is made whether a material associated with the at least one of the multiple spectral images is a hazardous material. Personnel is notified that the at least one radiation source is a hazardous material.

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 neutron detector includes a photo sensor with an electrical signal output electrically connected with an electrical signal input node of an electrical signal amplifier circuit. A resistive load is electrically connected between the electrical signal input node and a reference voltage node. The resistive load is a smaller resistance than an open circuit input resistance of the electrical signal amplifier circuit at the electrical signal input node thereby reducing the effective input resistance of the amplifier as seen by the photo sensor's electrical signal output. The neutron detector includes a set of scintillation layers connected to a light guide that channels light to the photo sensor. Moderator material is applied around the set of layers reducing thermal neutron absorption within the detector and increasing detector efficiency.

Abstract: A hazardous materials detection and identification system includes a set of distributed sensors across one or more sides of a self propelled frame structure such as a straddle carrier or similar cargo equipment device. The system non-invasively analyzes vehicles, one or more containers in a stack, a container during lift and movement, a package, cargo, or other objects, that are located in an analysis position relative to the self propelled frame structure for detection and identification of hazardous materials such as chemicals, biological materials, radiological materials, fissile materials, and explosives (CBRNE).

Abstract: A sensor interface system interfaces a collection of one or more sensors that can sense chemical, biological, radiation, nuclear, and explosives (CBRNE) materials. The system includes one or more digital and/or analog sensor interfaces for communicating with one or more sensors including: chemical sensors, biological sensors, radiation sensors, nuclear sensors, and explosives sensors. A processor is configured to receive and process signals from the one or more digital and/or analog sensor interfaces, and when the one or more sensors include a radiation sensor and/or nuclear sensor, the processor differentiates between gamma pulses and neutron pulses, by: receiving a signal from an output of a neutron detector; analyzing a pulse shape of the signal; differentiating the pulse shape between gamma pulses and neutron pulses; and determining that the pulse shape of the signal is one of a gamma pulse and a neutron pulse.

Abstract: A semi-closed loop diesel photobioreactor system and method are provided for producing diesel fuel from wild algae or from specialized algae that has been biologically modified for high efficiency oil production using waste water as a primary food source. The diesel photobioreactor provides a semi-closed loop system with an opening to acquire waste water below the surface to obtain waste water nutrients and to protect the algae species from contamination. The semi-closed loop diesel photobioreactor includes a container that can be designed in a variety of shapes with a tube design preferred, and containing a liquid culture medium for cultivating photosynthetic organisms. The system can utilize natural light and can also deploy an innovative lighting system integrated into the photobioreactor container. The diesel photobioreactor system also has one or more cleaning devices mounted within the container for cleaning the surface of the photobioreactor container.

Abstract: A system, method, and floating intelligent perimeter sensor, provide protection for waterways and critical infrastructures. The system and method utilize one or more floating intelligent perimeter sensors to detect, and in some cases identify, hazardous materials associated with vessels in the waterways. The hazardous materials detected, and optionally identified, can include radiological materials, fissile materials, explosives, chemicals and biological materials (CBRNE). A set of radiation data associated with a radiation source in a vessel is received from the one or more floating intelligent perimeter sensors. At least one histogram is generated based on the set of radiation data. The at least one histogram is compared to multiple spectral images associated with known materials. The at least one histogram is determined to substantially match at least one of the multiple spectral images. A determination is made whether a material associated with the radiation source is a hazardous material.

Abstract: A system and method determine a direction associated with gamma and/or neutron radiation emissions. A first radiation photon count associated with a first detector in a detector set is received from the first detector. The first radiation photon count is associated with at least one radiation source. A second radiation photon count associated with a second detector in the detector set is received from the second detector. The first radiation photon count is compared to the second radiation photon count. One of the first detector and the second detector is identified to have detected a larger number of radiation photons than the other. The at least one radiation source is determined to be substantially in a direction in which the one of the first detector and the second detector that has detected the larger number of radiation photons is facing.

Abstract: A chemical and biological sensor system (200) includes at least one micro-cantilever sensing element (202) and a mechanism for collecting aerosol, liquid, and solid particles, and depositing the particles as a film layer (146) on a stack (140) formed with the cantilever. The deposited particles include chemical or biological species to be analyzed. A polarized light (242) illuminates the stack (140) at a grazing incidence angle to a specific wavelength of light. The light is polarized in a plane parallel to the stack (140). The polarized light (242) heats the cantilever with different wavelengths of the light spectrum. Readout electronics detect movement of the cantilever (202) as a result of heat transfer from the light and provide spectral data signals corresponding to the detected movement. A spectral analyzer (840) analyzes the spectral data signals, compares spectral images of the materials present to spectral images of known materials, and identifies one or more chemical or biological species present.

Abstract: A multi-stage process utilizing one or more radiation sensors on a distributed network for the detection and identification of radiation, explosives, and special materials within a shipping container. The sensors are configured as nodes on the network. The system collects radiation data from one or more nodes. The collected radiation data is dynamically adjusted according to at least one of a plurality of background radiation data based on a determined background environment about the container. The collected and adjusted radiation data is compared to one or more stored spectral images representing one or more isotopes to identify one or more isotopes present. The identified one or more isotopes present are corresponded to possible materials or goods that they represent.

Abstract: A multi-stage process utilizing one or more radiation sensors on a distributed network for the detection and identification of radiation, explosives, and special materials within a shipping container. The sensors are configured as nodes on the network. The system supports extended time options at each node and the ability to combine data from multiple nodes for the data acquisition and analysis of shipping containers. The system collects radiation data from one or more nodes and compares the collected data to one or more stored spectral images representing one or more isotopes to identify one or more isotopes present. The identified one or more isotopes present are corresponded to possible materials or goods that they represent. The possible materials or goods are compared with the manifest relating to the container to confirm the identity of materials or goods contained in the container or to detect and/or identify unauthorized materials or goods in the container.

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 radiation shielding system includes at a first shielding member and at least a second shielding member that is coupled to the first shielding member. Each of the first and second shielding member includes a moderator material. At least the first shielding member includes at least one locking member extending from a surface of a region where the at least one locking member is disposed. At least the second shielding member includes at least one recessed area on a side of the second shielding member corresponding to the side of the first shielding member. The second shielding member is coupled to the first shielding member by the recessed area receiving the locking member.

Abstract: A scintillator system is provided to detect the presence of fissile material and radioactive material. One or more neutron detectors include scintillator material, and are optically coupled to one or more wavelength shifting fiber optic light guide media that extend from the scintillator material to guide light from the scintillator material to a photosensor. An electrical output of the photosensor is connected to an input of a pre-amp circuit designed to provide an optimum pulse shape for each of neutron pulses and gamma pulses in the detector signals. Scintillator material as neutron detector elements can be spatially distributed with interposed moderator material. Individual neutron detectors can be spatially distributed with interposed moderator material. Detectors and moderators can be arranged in a V-shape or a corrugated configuration.

Abstract: A chemical and biological sensor system (200) includes at least one micro-cantilever sensing element (202) and a mechanism for collecting aerosol, liquid, and solid particles, and depositing the particles as a film layer (146) on a stack (140) formed with the cantilever. The deposited particles include chemical or biological species to be analyzed. A polarized light (242) illuminates the stack (140) at a grazing incidence angle to a specific wavelength of light. The light is polarized in a plane parallel to the stack (140). The polarized light (242) heats the cantilever with different wavelengths of the light spectrum. Readout electronics detect movement of the cantilever (202) as a result of heat transfer from the light and provide spectral data signals corresponding to the detected movement. A spectral analyzer (840) analyzes the spectral data signals, compares spectral images of the materials present to spectral images of known materials, and identifies one or more chemical or biological species present.

Abstract: A multi-stage process utilizing one or more radiation sensors on a distributed network for the detection and identification of radiation, explosives, and special materials within a shipping container. The sensors are configured as nodes on the network. The system collects radiation data from one or more nodes. The collected radiation data is dynamically adjusted according to at least one of a plurality of background radiation data based on a determined background environment about the container. The collected and adjusted radiation data is compared to one or more stored spectral images representing one or more isotopes to identify one or more isotopes present. The identified one or more isotopes present are corresponded to possible materials or goods that they represent.