The present invention relates to a system for monitoring electrical properties of materials of deep bedrock samples for estimating nuclide movement in disposal site of spent fuel and, more specifically, to a system for monitoring electrical properties of materials of deep bedrock samples for estimating nuclide movement in disposal site of spent fuel which installs a tube wherein ring-shaped potential electrode is formed in multi layers inside a column; adheres the potential electrode to deep bedrock samples by pressing on the external side of the tube while filling the deep bedrock samples inside of the tube; and reproduces real condition of deep bedrock and monitors precisely by measuring electrical resistivity for each location of the deep bedrock samples while injecting nuclide and underground water to the inside the tube.

The present invention relates to a method for simultaneous analysis of radiocarbon and tritium, the method including (i) mixing a radioactive waste sample containing a radiocarbon nuclide and tritiated water, and an oxidizing agent; (ii) oxidizing the radiocarbon nuclide in the radioactive waste sample to a gas containing an oxide of the radiocarbon nuclide by the oxidizing agent while suppressing volatilization of compounds containing gamma radionuclides other than the radiocarbon nuclide and tritium; (iii) discharging the gas containing an oxide of the radiocarbon nuclide by injecting an inert gas to the mixture; (iv) vaporizing and discharging the tritiated water in the mixture; and (v) analyzing radioactivity of radiocarbon and tritium from the discharged gas containing an oxide of the radiocarbon nuclide and tritiated water, and an apparatus for analysis of the same.

The present invention relates to a method for simultaneous analysis of radiocarbon and tritium, the method including (i) mixing a radioactive waste sample containing a radiocarbon nuclide and tritiated water, and an oxidizing agent; (ii) oxidizing the radiocarbon nuclide in the radioactive waste sample to a gas containing an oxide of the radiocarbon nuclide by the oxidizing agent while suppressing volatilization of compounds containing gamma radionuclides other than the radiocarbon nuclide and tritium; (iii) discharging the gas containing an oxide of the radiocarbon nuclide by injecting an inert gas to the mixture; (iv) vaporizing and discharging the tritiated water in the mixture; and (v) analyzing radioactivity of radiocarbon and tritium from the discharged gas containing an oxide of the radiocarbon nuclide and tritiated water, and an apparatus for analysis of the same.

For determining whether oil waste at a field testing site is exempt from selected naturally occurring radioactive material (NORM) waste regulations, a measurement apparatus including a detection module that determine radioactivity counts per minute for an oil waste sample is utilized. The measurement apparatus includes an analysis module that uses a first nonlinear transfer function to determine a mass for the oil waste based on a volume of solids determined via BS&W testing. The analysis module uses a second nonlinear transfer function to determine a maximum radioactivity level for the sample which is then normalized to picoCuries/g. The normalized maximum radioactivity level per gram is compared to a NORM exemption level for a selected region and communicated to entities at the field-testing site and optionally to other entities. A system and a method perform the functions of the measurement apparatus.

For determining whether oil waste at a field testing site is exempt from selected naturally occurring radioactive material (NORM) waste regulations, a measurement apparatus including a detection module that determine radioactivity counts per minute for an oil waste sample is utilized. The measurement apparatus includes an analysis module that uses a first nonlinear transfer function to determine a mass for the oil waste based on a volume of solids determined via BS&W testing. The analysis module uses a second nonlinear transfer function to determine a maximum radioactivity level for the sample which is then normalized to picoCuries/g. The normalized maximum radioactivity level per gram is compared to a NORM exemption level for a selected region and communicated to entities at the field-testing site and optionally to other entities. A system and a method perform the functions of the measurement apparatus.

The present disclosure provides a gamma camera imaging method and a gamma camera imaging device. The method includes: selecting, from energy spectrums captured by a gamma camera on one or more radioactive materials, one or more energy ranges of each radioactive material among the one or more radioactive materials as one or more monitored energy regions of the radioactive material; performing image reconstruction on the monitored energy regions of each radioactive material among the one or more radioactive materials; performing normalization on images obtained through the image reconstruction; and performing superimposing on the normalized images to form a composite image.

The present disclosure provides a gamma camera imaging method and a gamma camera imaging device. The method includes: selecting, from energy spectrums captured by a gamma camera on one or more radioactive materials, one or more energy ranges of each radioactive material among the one or more radioactive materials as one or more monitored energy regions of the radioactive material; performing image reconstruction on the monitored energy regions of each radioactive material among the one or more radioactive materials; performing normalization on images obtained through the image reconstruction; and performing superimposing on the normalized images to form a composite image.

A radiation dosimetry gel is excellent in heat resistance, and a radiation dosimeter includes the radiation dosimetry gel as a material for measuring a radiation dose. A radiation dosimetry gel includes a water-soluble organic polymer (A) having an organic acid salt structure or an organic acid anion structure, a silicate (B), and a dispersant (C) for the silicate, and a radiation dosimeter includes the radiation dosimetry gel as a material for measuring a radiation dose.

A radiation dosimetry gel is excellent in heat resistance, and a radiation dosimeter includes the radiation dosimetry gel as a material for measuring a radiation dose. A radiation dosimetry gel includes a water-soluble organic polymer (A) having an organic acid salt structure or an organic acid anion structure, a silicate (B), and a dispersant (C) for the silicate, and a radiation dosimeter includes the radiation dosimetry gel as a material for measuring a radiation dose.

A method for calibrating an ionising radiation detector, with the aim of determining a correction factor in order to establish an amplitude-energy correspondence The invention first relates to a method for calibrating a device for detecting ionising radiation, the detector comprising a semiconductor or scintillator detection material capable of generating a signal S of amplitude A upon interaction between ionising radiation and the detection material, the method including the determination of a weighting factor of amplitude A.