Abstract: It is disclosed a blood glucose prediction system and method using saliva-based artificial intelligence deep learning technique.

Abstract: An apparatus for filtering airborne radioactive iodine is provided. The apparatus includes a housing defining an interior space and comprising an inlet for receiving air and an outlet for discharging the air; and a composition placed in the interior space for trapping airborne radioactive iodine between the inlet and the outlet. The composition comprises one or more salts selected from the group consisting of an alkali metal chloride and an alkaline earth metal chloride. A method of filtering airborne radioactive iodine is further provided. The method includes providing the foregoing apparatus at a nuclear facility and blowing air to flow from the inlet to the outlet and contact the composition placed in the interior space, whereby airborne radioactive iodine is trapped in the interior space.

Abstract: An apparatus for filtering airborne radioactive iodine is provided. The apparatus includes a housing defining an interior space and comprising an inlet for receiving air and an outlet for discharging the air; and a composition placed in the interior space for trapping airborne radioactive iodine between the inlet and the outlet. The composition comprises one or more salts selected from the group consisting of an alkali metal chloride and an alkaline earth metal chloride. A method of filtering airborne radioactive iodine is further provided. The method includes providing the foregoing apparatus at a nuclear facility and blowing air to flow from the inlet to the outlet and contact the composition placed in the interior space, whereby airborne radioactive iodine is trapped in the interior space.

Abstract: A neutron detector composed of a matrix of scintillating particles imbedded in a lithiated glass is disclosed. The neutron detector detects the neutrons by absorbing the neutron in the lithium-6 isotope which has been enriched from the natural isotopic ratio to a commercial ninety five percent. The utility of the detector is optimized by suitably selecting scintillating particle sizes in the range of the alpha and the triton. Nominal particle sizes are in the range of five to twenty five microns depending upon the specific scintillating particle selected.

Abstract: Applicant's present invention is a composite scintillator for neutron detection comprising a matrix material fabricated from an inorganic sol-gel precursor solution homogeneously doped with a liquid scintillating material and a neutron absorbing material. The neutron absorbing material yields at least one of an electron, a proton, a triton, an alpha particle or a fission fragment when the neutron absorbing material absorbs a neutron. The composite scintillator further comprises a liquid scintillating material in a self-assembled micelle formation homogeneously doped in the matrix material through the formation of surfactant-silica composites. The scintillating material is provided to scintillate when traversed by at least one of an electron, a proton, a triton, an alpha particle or a fission fragment. The scintillating material is configured such that the matrix material surrounds the micelle formation of the scintillating material.

Abstract: Applicant's present invention is a composite scintillator for neutron detection comprising a matrix material fabricated from an inorganic sol-gel precursor solution homogeneously doped with a liquid scintillating material and a neutron absorbing material. The neutron absorbing material yields at least one of an electron, a proton, a triton, an alpha particle or a fission fragment when the neutron absorbing material absorbs a neutron. The composite scintillator further comprises a liquid scintillating material in a self-assembled micelle formation homogeneously doped in the matrix material through the formation of surfactant-silica composites. The scintillating material is provided to scintillate when traversed by at least one of an electron, a proton, a triton, an alpha particle or a fission fragment. The scintillating material is configured such that the matrix material surrounds the micelle formation of the scintillating material.

Abstract: A neutron detector composed of a matrix of scintillating particles imbedded in a lithiated glass is disclosed. The neutron detector detects the neutrons by absorbing the neutron in the lithium-6 isotope which has been enriched from the natural isotopic ratio to a commercial ninety five percent. The utility of the detector is optimized by suitably selecting scintillating particle sizes in the range of the alpha and the triton. Nominal particle sizes are in the range of five to twenty five microns depending upon the specific scintillating particle selected.