A portable electronic dosimeter is described that comprises a plurality of detectors each configured to detect a type of ionizing radiation, wherein each detector is associated with an amplifier configured to produce an output in response to a plurality of detected photons of the ionizing radiation and an event counter configured to produce one or more counts in response to the detected photons of the ionizing radiation over an integration time; and a processor configured to receive the one or more counts from each of the counters and determine if there is coincidence of the one or more counts of all the detectors, wherein if there is coincidence the processor is configured to provide an over range alarm signal.

A portable electronic dosimeter is described that comprises a plurality of detectors each configured to detect a type of ionizing radiation, wherein each detector is associated with an amplifier configured to produce an output in response to a plurality of detected photons of the ionizing radiation and an event counter configured to produce one or more counts in response to the detected photons of the ionizing radiation over an integration time; and a processor configured to receive the one or more counts from each of the counters and determine if there is coincidence of the one or more counts of all the detectors, wherein if there is coincidence the processor is configured to provide an over range alarm signal.

A neutron spectrum generator is disclosed herein including a neutron source, a scatterer positioned in a direct path between the neutron source and a neutron detector, and a material shell configured to have at least one non-uniform characteristic selected from the group consisting of a material, a thickness, a length, an angle, a layer, and combinations thereof to generate a specific spectrum at the neutron detector that is different than the spectrum of the neutron source. A related method includes measuring a first response generated by a first material shell of a neutron spectrum generator interacting with a neutron source, replacing the first material shell with a second material shell, measuring a second response generated by a second material shell of a neutron spectrum generator interacting with the neutron source, and determining a total fission response by determining a difference between the first response and the second response.

An isotropic neutron detector includes a spherical secondary particle radiator component and a plurality of stacked semiconductor detectors, A first semiconductor detector is coupled to at least a portion of the spherical secondary particle radiator component, forming a portion of a first concentric shell thereover. A second semiconductor detector coupled to at least a portion of the first semiconductor detector, forming a portion of a second concentric shell thereover.

The present application relates to a method for coating boron, to a boron-containing resin solution, to a boron-coated thermal neutron converter obtained by the method for coating boron, and further to a thermal neutron detector comprising the boron-coated thermal neutron converter. The method for coating boron as provided in the application is applicable for various substrates and has small restrictions on substrate shapes, particularly for substrates having complex surface structures and high aspect ratios.

The present application relates to a method for coating boron, to a boron-containing resin solution, to a boron-coated thermal neutron converter obtained by the method for coating boron, and further to a thermal neutron detector comprising the boron-coated thermal neutron converter. The method for coating boron as provided in the application is applicable for various substrates and has small restrictions on substrate shapes, particularly for substrates having complex surface structures and high aspect ratios.

A system and method for making a neutron detector includes stacking anode frames and laminated frames to form a detector insert. The laminated frames are formed by laminating a foil of neutron-responsive material to an aluminum frame plated with a metal that does not react with the neutron-responsive material. The anode frames include an anode wire tensioned to a predetermined tension. The anode wires are electrically coupled to a top lid that includes an electrical connector and a gas feed through. The top lid is pressed into a tank with the detector insert.

A system and method for making a neutron detector includes stacking anode frames and laminated frames to form a detector insert. The laminated frames are formed by laminating a foil of neutron-responsive material to an aluminum frame plated with a metal that does not react with the neutron-responsive material. The anode frames include an anode wire tensioned to a predetermined tension. The anode wires are electrically coupled to a top lid that includes an electrical connector and a gas feed through. The top lid is pressed into a tank with the detector insert.

A ceramic lithium indium diselenide or like radiation detector device formed as a pressed material that exhibits scintillation properties substantially identical to a corresponding single crystal growth radiation detector device, exhibiting the intrinsic property of the chemical compound, with an acceptable decrease in light output, but at a markedly lower cost due to the time savings associated with pressing versus single crystal growth.

A ceramic lithium indium diselenide or like radiation detector device formed as a pressed material that exhibits scintillation properties substantially identical to a corresponding single crystal growth radiation detector device, exhibiting the intrinsic property of the chemical compound, with an acceptable decrease in light output, but at a markedly lower cost due to the time savings associated with pressing versus single crystal growth.