A system for monitoring ionizing radiation in a target area, the system may include a first plurality of consumable nodes deployable within the target area to be exposed to the ionizing radiation. Each consumable node may be progressively damageable over a monitoring time as a result of exposure to the ionizing radiation. A base station may be operable to detect an amount of radiation damage sustained by the consumable nodes and to determine a dosage of ionizing radiation received by any one of the consumable nodes based on a pre-determined correlation between the dosage of ionizing radiation and the amount of radiation damage sustained by the consumable node.

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.

Upon blood collection with a disclosed blood collecting apparatus, a part of a flow path adjacent to a suction drain mechanism is filled with a liquid different from the blood. A gas is inserted in the flow path between the liquid with which the part of the flow path adjacent to the suction drain mechanism is filled and a target blood to be collected. The suction drain mechanism pushes and pulls the gas by pushing and pulling the liquid during a standby time between collection and next collection, thereby controlling movement of the target blood. The suction drain mechanism pushes and pulls the liquid and the gas during the standby time, whereby the target blood is continuously moved. This allows prevention of coagulation of the target blood in the flow path.

Upon blood collection with a disclosed blood collecting apparatus, a part of a flow path adjacent to a suction drain mechanism is filled with a liquid different from the blood. A gas is inserted in the flow path between the liquid with which the part of the flow path adjacent to the suction drain mechanism is filled and a target blood to be collected. The suction drain mechanism pushes and pulls the gas by pushing and pulling the liquid during a standby time between collection and next collection, thereby controlling movement of the target blood. The suction drain mechanism pushes and pulls the liquid and the gas during the standby time, whereby the target blood is continuously moved. This allows prevention of coagulation of the target blood in the flow path.

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.

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.

Techniques for testing subterranean water for one or more radioactive isotopes for a hazardous waste material repository include collecting, from a test drillhole formed from a terranean surface to a subterranean formation, a subterranean water sample from the subterranean formation; determining, with an accelerator mass spectrometry (AMS) system, a concentration of a radioactive isotope of an element in the subterranean water sample relative to a stable isotope of the element in the subterranean water sample; comparing the determined concentration of the radioactive isotope of the element in the subterranean water sample with a concentration of the radioactive isotope of the element in a surface water sample relative to the stable isotope of the element in the surface water sample; and based on the determined concentration of the radioactive isotope in the subterranean water sample being a specified percentage of the concentration of the radioactive isotope in the surface water sample, determining that the subterranean formation is a hazardous waste storage repository.