A control apparatus may include a processor for calculating a detection efficiency, which is detected by a gamma-ray detection unit, of gamma-rays emitted from a sample stuffed into a first container. A shape of the first container is a shape which surrounds at least a part of the gamma-ray detection unit that detects the gamma-rays. An area inside the first container is divided into a plurality of similar areas which is area similar in shape to each other. The gamma-ray detection unit detects the gamma-rays emitted from the sample included in each the similar areas for each of the plurality of similar areas. The processor calculates the detection efficiency as a similar-area-detection efficiency based on a result of detection performed by the gamma-ray detection unit.

A control apparatus may include a processor for calculating a detection efficiency, which is detected by a gamma-ray detection unit, of gamma-rays emitted from a sample stuffed into a first container. A shape of the first container is a shape which surrounds at least a part of the gamma-ray detection unit that detects the gamma-rays. An area inside the first container is divided into a plurality of similar areas which is area similar in shape to each other. The gamma-ray detection unit detects the gamma-rays emitted from the sample included in each the similar areas for each of the plurality of similar areas. The processor calculates the detection efficiency as a similar-area-detection efficiency based on a result of detection performed by the gamma-ray detection unit.

A bin for use in a security checkpoint can include a receptacle surface, sidewalls, a lip provided on the sidewalls, and a geometrical marker. The geometrical marker is radiographically, visually, and tactilely detectable on the lip of one side of the bin. The geometrical marker includes a plurality of tag elements.

A bin for use in a security checkpoint can include a receptacle surface, sidewalls, a lip provided on the sidewalls, and a geometrical marker. The geometrical marker is radiographically, visually, and tactilely detectable on the lip of one side of the bin. The geometrical marker includes a plurality of tag elements.

A primary sample holder for imaging, gross pathology, or histological correlations of a biological sample includes an enclosure having a first side wall, a second side wall, and a bottom wall; a plurality of slots provided at predetermined intervals along the first and second side walls; and a grid recessed within the bottom wall. The grid includes a hole bisected by a central panel and at least one axial panel that intersects the central panel along a length thereof. The biological sample received by the primary sample holder is configured to be aligned with the central panel of the grid to align the biological sample along an accepted internal orientation line (e.g., the anterior-posterior commissure line in the brain). The slots are configured to receive a cutting device to cut the biological sample into slices of uniform thickness containing a region of interest based on histological and imaging findings.

A primary sample holder for imaging, gross pathology, or histological correlations of a biological sample includes an enclosure having a first side wall, a second side wall, and a bottom wall; a plurality of slots provided at predetermined intervals along the first and second side walls; and a grid recessed within the bottom wall. The grid includes a hole bisected by a central panel and at least one axial panel that intersects the central panel along a length thereof. The biological sample received by the primary sample holder is configured to be aligned with the central panel of the grid to align the biological sample along an accepted internal orientation line (e.g., the anterior-posterior commissure line in the brain). The slots are configured to receive a cutting device to cut the biological sample into slices of uniform thickness containing a region of interest based on histological and imaging findings.

The present invention relates to a drying apparatus for drying a canister configured to transport and store spent nuclear fuels, a control method thereof, and a radiation shielding geometry for a radiation dosimeter configured to measure a radiation dose rate. An object of the present invention is to prevent a drying apparatus from being contaminated even in case of a damaged canister loaded with a spent nuclear fuel, by providing a non-contaminated circulation system and a contaminated circulation system, to easily assemble the drying apparatus to have a proper thickness depending upon a radiation dose rate, and to prevent a facility pipeline from being under stress by providing a radiation shielding geometry for a radiation dosimeter for measuring a radiation dose rate.

The present invention relates to a drying apparatus for drying a canister configured to transport and store spent nuclear fuels, a control method thereof, and a radiation shielding geometry for a radiation dosimeter configured to measure a radiation dose rate. An object of the present invention is to prevent a drying apparatus from being contaminated even in case of a damaged canister loaded with a spent nuclear fuel, by providing a non-contaminated circulation system and a contaminated circulation system, to easily assemble the drying apparatus to have a proper thickness depending upon a radiation dose rate, and to prevent a facility pipeline from being under stress by providing a radiation shielding geometry for a radiation dosimeter for measuring a radiation dose rate.

The present disclosure provides a gamma-ray attenuator and a gamma-ray shield for use in gamma-ray spectroscopy. The gamma-ray attenuator is a sleeve comprising a wall, a distal end, and a proximal end. The distal end of the sleeve is closed, and the proximal end of the sleeve forms an opening. A copper insert, a tin insert and a tungsten insert are installed in the sleeve such that the copper insert is adjacent to the distal end and the tungsten insert is closest to the proximal end. The sleeve is comprised of one or more materials that do not substantially attenuate gamma-rays. The open end of the sleeve fits over a tungsten safe that is operable to hold a radionuclide sample. When fitted together, a gamma-ray attenuator and a safe comprise a gamma-ray shield.

An infusion system may include a radioisotope generator that generates a radioactive eluate via elution, a beta detector, a gamma detector, and a controller. The beta detector and the gamma detector may be positioned to measure beta emissions and gamma emissions, respectively, emitted from the radioactive eluate. In some examples, the controller is configured to calibrate the infusion system using the gamma detector. For example, the controller may generate a radioactive eluate and measure the activity of the radioactive eluate using both the beta detector and the gamma detector. The high accuracy of the activity measured by the gamma detector may be used to calibrate the infusion system. In subsequent use, the infusion system calibrated using the gamma detector may adjust measurements made to monitor and/or control patient infusion procedures.