A method for joint measuring argon-argon age and cosmic ray exposure age of an extraterrestrial sample is provided. The method for joint measuring determining argon age and cosmic ray exposure age may include: step A, sample packaging; step B, placing the packaged samples into a neutron reactor for irradiation; and step C, determining Ar isotopes of the packaged samples after being performed with a neutron irradiation and thereby calculating argon-argon age and cosmic ray exposure age. The method can overcome the defects of the prior art, and achieve high-precision simultaneous determination of the argon-argon age and the cosmic ray exposure age of samples.

A device configured to measure radioactivity emitted by a plurality of radionuclides is disclosed herein. The device includes a gamma detector and a source cage with an outer ring that defines a volume and includes an orientation feature and a plurality of holes configured to receive a radionuclide of the plurality of radionuclides. The device also includes a frame that includes an arm and a central rod, wherein the arm is configured to be coupled to the outer ring and includes an orientation pin. The central rod can be positioned relative to the volume when the arm is coupled to the outer ring of source cage. The orientation feature of the source cage is configured to engage the orientation pin of the arm and, when the orientation pin engages the orientation feature, the central rod is in a predetermined location relative to the volume.

Disclosed are a method and a device for recovering uranium (U) using a process for chemically treating washing wastewater of a uranium hexafluoride (UF6) cylinder. The method and the device are provided to separate uranium (U) from the wastewater released during a process of washing the uranium hexafluoride (UF6) cylinder and to release a filtrate that satisfies atomic energy licensing standards and environmental regulation standards using evaporation and condensation. Accordingly, an independent technology and process for treating the wastewater released during the process of washing the uranium hexafluoride (UF6) cylinder are ensured, which provides easier maintenance and greatly reduces costs compared to the purchase and operation of apparatuses manufactured by foreign makers.

Disclosed are a method and a device for recovering uranium (U) using a process for chemically treating washing wastewater of a uranium hexafluoride (UF6) cylinder. The method and the device are provided to separate uranium (U) from the wastewater released during a process of washing the uranium hexafluoride (UF6) cylinder and to release a filtrate that satisfies atomic energy licensing standards and environmental regulation standards using evaporation and condensation. Accordingly, an independent technology and process for treating the wastewater released during the process of washing the uranium hexafluoride (UF6) cylinder are ensured, which provides easier maintenance and greatly reduces costs compared to the purchase and operation of apparatuses manufactured by foreign makers.

In one embodiment, there is provided a system for inspection of a human or animal body, comprising: a radiation provider configured to provide ionizing radiation having a radiation dose to the body, for inspection of the body by transmission; a measurement device configured to measure other than the ionizing radiation to determine at least one property associated with a dimension of the body to inspect; and a controller configured to cause the radiation dose provided to the body by the radiation provider to be controlled based on the at least one property determined by the measurement device.

In one embodiment, there is provided a system for inspection of a human or animal body, comprising: a radiation provider configured to provide ionizing radiation having a radiation dose to the body, for inspection of the body by transmission; a measurement device configured to measure other than the ionizing radiation to determine at least one property associated with a dimension of the body to inspect; and a controller configured to cause the radiation dose provided to the body by the radiation provider to be controlled based on the at least one property determined by the measurement device.

Provided herein are neutron-based detection systems and methods that provide, for example, high throughput analysis of elemental analysis of scrap materials. Such systems and methods find use for the commercial-scale evaluation of bulk process materials where hazardous or otherwise undesirable materials or high value materials may be interspersed with the primary process material. In certain embodiments, the system is used to detect and potentially remove unexploded ordinance (UXO) from a conveyor of demilitarized shell casings being recycled by detecting the presence of nitrogen and other elements present in the UXO. In other embodiments, the system detects and removes unwanted or highly valuable materials from a stream of scrap material.

A radon management system using a radon detector is proposed. The system includes: at least one radon detector installed in a specific space indoors or outdoors, and configured to detect in real time alpha particles present in the specific space, output a predetermined alpha particle detection signal, count for a preset measurement time to calculate and transmit an alpha particle concentration value, and transmit unique device identification information; and a radon management server configured to collect the unique device identification information and alpha particle concentration value, calculate and quantify an average value of the collected alpha particle concentration values to be converted into a database for each radon detector, store and manage the average value, compare the alpha particle concentration value and the average values of the previously stored alpha particle concentration value to each other to calculate a change amount thereof, and generate radon generation event information data.

A radon management system using a radon detector is proposed. The system includes: at least one radon detector installed in a specific space indoors or outdoors, and configured to detect in real time alpha particles present in the specific space, output a predetermined alpha particle detection signal, count for a preset measurement time to calculate and transmit an alpha particle concentration value, and transmit unique device identification information; and a radon management server configured to collect the unique device identification information and alpha particle concentration value, calculate and quantify an average value of the collected alpha particle concentration values to be converted into a database for each radon detector, store and manage the average value, compare the alpha particle concentration value and the average values of the previously stored alpha particle concentration value to each other to calculate a change amount thereof, and generate radon generation event information data.

A method for multidimensional direction measurement of gamma radiation in the far field by means of a group of several energy discriminating detectors synchronized with each other for detection of radiation can use unidirectional and bidirectional Compton scattering processes and lookup tables LUT.sup.SK, a defined functional value f(E1,E2), a list of defined detector pairs with an identification number i for defined detector pairs, and one or more frequency distributions Y for the acquisition of the measurement values. In some embodiments, the method can include setting up a detector system, acquiring measurement values, associating coincidence events with an Identification number, calculating a functional value, acquiring coincidence events in frequency distributions, and calculating one or more direction distributions from the frequency distributions.