A shield structure configured to protect a head and/or neck of a patient during a radiologic procedure comprises a bottom wall, a side wall, and an opening. The bottom wall includes radiation attenuating material and is configured to be positioned between the head and/or neck of the patient and a radiation source so as to shield the patient from radiation directed toward the bottom of the patient. The bottom wall is of a general size to shield the head and/or neck of the patient. The side wall includes radiation attenuating material and is configured to extend upward from the bottom wall so as to shield the patient from radiation directed toward a side of the patient. The opening is configured to receive the head and/or neck of the patient.

An apparatus is provided for storing hazardous waste material, which includes one or more of spent nuclear fuel, radioactive material, and fissionable material. A fusible alloy material, for example, a eutectic material, resides within the apparatus and surrounds the hazardous waste material. In the preferred embodiments, it is suggested that the fusible alloy material exhibits liquidus and solidus or melting temperatures that are between about 100 and 300 degrees Fahrenheit for facilities using the apparatus and methods for liquid storage pool loading applications. For facilities using the apparatus and methods for dry loading, the fusible alloy materials may exhibit liquidus and solidus or melting temperatures that are between about 100 and 650 degrees Fahrenheit. The fusible alloy material is introduced in a liquid phase and eventually solidifies into a solid phase as the temperature of the hazardous waste material and/or the local environment decreases.

An apparatus is provided for storing hazardous waste material, which includes one or more of spent nuclear fuel, radioactive material, and fissionable material. A fusible alloy material, for example, a eutectic material, resides within the apparatus and surrounds the hazardous waste material. In the preferred embodiments, it is suggested that the fusible alloy material exhibits liquidus and solidus or melting temperatures that are between about 100 and 300 degrees Fahrenheit for facilities using the apparatus and methods for liquid storage pool loading applications. For facilities using the apparatus and methods for dry loading, the fusible alloy materials may exhibit liquidus and solidus or melting temperatures that are between about 100 and 650 degrees Fahrenheit. The fusible alloy material is introduced in a liquid phase and eventually solidifies into a solid phase as the temperature of the hazardous waste material and/or the local environment decreases.

Systems, devices, and methods are described for providing, among other things, an intra-oral x-ray imaging system configured to reduce patient exposure to x-rays, reduce amount of scatter, transmission, or re-radiation during imaging, or improve x-ray image quality. In an embodiment, an intra-oral x-ray imaging system includes an intra-oral x-ray sensor configured to communicate intra-oral x-ray sensor position information or intra-oral x-ray sensor orientation information to a remote x-ray source.

Systems, devices, and methods are described for providing, among other things, an intra-oral x-ray imaging system configured to reduce patient exposure to x-rays, reduce amount of scatter, transmission, or re-radiation during imaging, or improve x-ray image quality. In an embodiment, an intra-oral x-ray imaging system includes an intra-oral x-ray sensor configured to communicate intra-oral x-ray sensor position information or intra-oral x-ray sensor orientation information to a remote x-ray source.

The present invention relates to rigid structures and composite materials thereof for providing radiation attenuation/shielding. Some embodiments pertain to a radiation shielding apparatus including: a plurality of positionable radiation-shielding stacks of tiles. The stacks are subsequently and adjacently arranged in a contiguous configuration. A tile positioning mechanism allows movement of tiles within a stack between a stacked (retracted) position and an extended position. In the extended position, the tiles of each of the plurality of radiation shielding stacks at least partially overlap tiles of subsequent and adjacent tile stack at corresponding opposing side-margins thereof.

A shielded X-ray radiation apparatus is provided comprising an X-ray source, an X-ray attenuation shield including an elongate cavity to house the X-ray source and incorporating a region to accommodate a sample, a neutron attenuation shield, and a gamma attenuation shield. The neutron attenuation shield is situated adjacent to and substantially surrounds the X-ray attenuation shield and the gamma attenuation shield is adjacent to and substantially surrounds the neutron attenuation shield. In some embodiments a removable sample insertion means is provided to insert samples into the elongate cavity and which is composed of adjacent blocks of material, each respective block having a thickness and a composition which substantially matches the thickness and a composition of one of the X-ray attenuation, neutron attenuation and gamma-ray attenuation shields.

A shielded X-ray radiation apparatus is provided comprising an X-ray source, an X-ray attenuation shield including an elongate cavity to house the X-ray source and incorporating a region to accommodate a sample, a neutron attenuation shield, and a gamma attenuation shield. The neutron attenuation shield is situated adjacent to and substantially surrounds the X-ray attenuation shield and the gamma attenuation shield is adjacent to and substantially surrounds the neutron attenuation shield. In some embodiments a removable sample insertion means is provided to insert samples into the elongate cavity and which is composed of adjacent blocks of material, each respective block having a thickness and a composition which substantially matches the thickness and a composition of one of the X-ray attenuation, neutron attenuation and gamma-ray attenuation shields.

A panel that uses the gamma radiation emitted by fission to produce electrical power. The panel includes layers of a metal with a relatively high atomic number (Z), that form an emitter, a high temperature electrical resistor, and an electrical conductor with a relatively low Z value, that forms a collector. The gamma radiation emitted during the fission process produces Compton and photoelectrical electrons in the layer of the Emitter located between the reactor Baffle and the fuel assemblies. The electrons that have sufficient energy to penetrate the resistor layer between the emitter layer and the collector layer will be stopped in the collector. This creates a substantial voltage difference between the emitter and the collector. This voltage difference may be used to produce significant electric power both during reactor operations and with the reactor shutdown to meaningfully augment the electricity produced by the turbine generators.

A panel that uses the gamma radiation emitted by fission to produce electrical power. The panel includes layers of a metal with a relatively high atomic number (Z), that form an emitter, a high temperature electrical resistor, and an electrical conductor with a relatively low Z value, that forms a collector. The gamma radiation emitted during the fission process produces Compton and photoelectrical electrons in the layer of the Emitter located between the reactor Baffle and the fuel assemblies. The electrons that have sufficient energy to penetrate the resistor layer between the emitter layer and the collector layer will be stopped in the collector. This creates a substantial voltage difference between the emitter and the collector. This voltage difference may be used to produce significant electric power both during reactor operations and with the reactor shutdown to meaningfully augment the electricity produced by the turbine generators.