A nuclear radiation detector is disclosed. The detector includes a housing including therein: a scintillator; and a multi-pixel optical sensor positioned, relative to the scintillator, to receive photons emitted by the scintillator in response to interactions with nuclear radiation. The housing isolates the scintillator and the multi-pixel optical sensor from external light. The detector includes one or more processors operably connectable to the multi-pixel optical sensor; and one or more data stores coupled to the processors having instructions stored thereon which cause the processors to perform operations. The operations include: responsive to the multi-pixel optical sensor detecting photons emitted by the scintillator, receiving, from the multi-pixel optical sensor, data signals indicating 1) spatial locations of individual pixels that detected the photons and 2) temporal data indicating when the detections occurred; and generating, from the data signals, a spatially and temporally resolved image of radiation incident on the scintillator.

The present invention relates to a Marinelli beaker correction container for stable radionuclide analysis, the Marinelli beaker correction container including: a container body having a diameter corresponding to a detector mounting part provided at a lower part of the Marinelli beaker, and being insertedly mounted to the detector mounting part; a detector coupling groove being formed at a lower part of the container body with an inner diameter corresponding to a diameter of the spectroscopy system detector, and allowing the Marinelli beaker to be mounted on the spectroscopy system detector by insertedly mounting the spectroscopy system detector to the detector coupling groove; and a ventilation hole being vertically formed through a center of a top surface of the container body, and allowing the container body to be smoothly mounted or dismounted due to air ventilation when the container body is mounted to or dismounted from the detector mounting part.

The present invention relates to a Marinelli beaker correction container for stable radionuclide analysis, the Marinelli beaker correction container including: a container body having a diameter corresponding to a detector mounting part provided at a lower part of the Marinelli beaker, and being insertedly mounted to the detector mounting part; a detector coupling groove being formed at a lower part of the container body with an inner diameter corresponding to a diameter of the spectroscopy system detector, and allowing the Marinelli beaker to be mounted on the spectroscopy system detector by insertedly mounting the spectroscopy system detector to the detector coupling groove; and a ventilation hole being vertically formed through a center of a top surface of the container body, and allowing the container body to be smoothly mounted or dismounted due to air ventilation when the container body is mounted to or dismounted from the detector mounting part.

A method for optimizing an aviation radiation dose comprises a) gathering flight-relevant data including at least one flight schedule; b) gathering radiation data including at least a current radiation field assigned to the at least one flight schedule, historical radiation data assigned to the flight-relevant data and a radiation dose threshold; c) calculating an expected radiation dose based on the flight-relevant data and the radiation data; and d) modifying the flight-relevant data and repeating steps a) to c) at least once in order to obtain optimized flight-relevant data with regard to the expected radiation dose. With each iteration the flight-relevant data is modified.

A method for optimizing an aviation radiation dose comprises a) gathering flight-relevant data including at least one flight schedule; b) gathering radiation data including at least a current radiation field assigned to the at least one flight schedule, historical radiation data assigned to the flight-relevant data and a radiation dose threshold; c) calculating an expected radiation dose based on the flight-relevant data and the radiation data; and d) modifying the flight-relevant data and repeating steps a) to c) at least once in order to obtain optimized flight-relevant data with regard to the expected radiation dose. With each iteration the flight-relevant data is modified.

A device for radioactivity counting and characterization for a solution. The device includes a container having at least two recesses, a first recess for receiving a vial and a second recess for receiving a radioactivity sensor, a radioactivity sensor having a semiconductor sensor presenting a cone of detection directed to the first recess of the container for receiving a vial, a removable closure element, an armored cover around the container and its upper face, the upper face of the armored cover having an opening for introducing the vial into the container and a plate for supporting the device.

A device for radioactivity counting and characterization for a solution. The device includes a container having at least two recesses, a first recess for receiving a vial and a second recess for receiving a radioactivity sensor, a radioactivity sensor having a semiconductor sensor presenting a cone of detection directed to the first recess of the container for receiving a vial, a removable closure element, an armored cover around the container and its upper face, the upper face of the armored cover having an opening for introducing the vial into the container and a plate for supporting the device.

An apparatus for analyzing nuclides and the concentration thereof in waste contained in a radioactive waste packaging container according to the present disclosure relates to an apparatus that has detector devices located above/under the waste packaging container and performs nuclide and concentration analysis on the waste in the packaging container by scanning the packaging container in the longitudinal direction thereof using a forward/backward driving device. In particular, upper/lower detector modules are equipped with multiple high-resolution gamma ray detectors to increase inspection efficiency, each module is designed to be driven up/down, and each detector in the module is designed to be driven left/right, thereby performing nuclide and concentration analysis on various types of packaging containers regardless of the size thereof.

An apparatus for analyzing nuclides and the concentration thereof in waste contained in a radioactive waste packaging container according to the present disclosure relates to an apparatus that has detector devices located above/under the waste packaging container and performs nuclide and concentration analysis on the waste in the packaging container by scanning the packaging container in the longitudinal direction thereof using a forward/backward driving device. In particular, upper/lower detector modules are equipped with multiple high-resolution gamma ray detectors to increase inspection efficiency, each module is designed to be driven up/down, and each detector in the module is designed to be driven left/right, thereby performing nuclide and concentration analysis on various types of packaging containers regardless of the size thereof.

Disclosed is a process method and system for upfront sampling and characterization to selectively and representatively sample for activation levels of nuclear reactor core irradiated metal alloy internal components using a specialized robust hard metal reactor bit hollow tungsten carbide sampling head in conjunction with bespoke angled sampling gantry. The invention relates to the field of a nuclear reactor metal alloy vacuum hollow sampling head, sampling gantry, and retrieval system. The nuclear-activated metal alloys are drilled and sampled using a TruProBit® metal cutting drill bit. The long hollow drill bit with a hollow metal sampling head traverses the nuclear reactor metal layers and void spaces to cut and retrieve only metal alloy samples. The dry vacuumed airflow picks up the discrete incremental sample of metal filings, chips, and dust produced by the hollow metal cutting edges of the sampling head into a filter and then analyzed for radionuclides of concern.