A gamma-ray analysis system is described for analyzing gamma-ray emitting radionuclides. The gamma-ray analysis system includes an analytical apparatus having a gamma-ray detector in operative communication with a modular and scalable shield assembly that encases a sample container having a sample to be tested. The detector communicates data to an electronic interface device that converts the data from an analog format to a digital format before a controller transmits the data to a central laboratory for further data processing, analysis and conclusion by qualified laboratory analysts. The controller runs an application software package on a graphic user interface that allows simple steps for conducting testing and data acquisition by the end user, while permitting real time data transmission between the field site and the central location. Functions were implemented for ensuring laboratory quality results while removing knowledge and experience requirements of an end user.

A gamma-ray analysis system is described for analyzing gamma-ray emitting radionuclides. The gamma-ray analysis system includes an analytical apparatus having a gamma-ray detector in operative communication with a modular and scalable shield assembly that encases a sample container having a sample to be tested. The detector communicates data to an electronic interface device that converts the data from an analog format to a digital format before a controller transmits the data to a central laboratory for further data processing, analysis and conclusion by qualified laboratory analysts. The controller runs an application software package on a graphic user interface that allows simple steps for conducting testing and data acquisition by the end user, while permitting real time data transmission between the field site and the central location. Functions were implemented for ensuring laboratory quality results while removing knowledge and experience requirements of an end user.

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.

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.

A .sup.14C testing bottle, a .sup.14C testing device, a .sup.14C testing method, a sampling and preparation system and its implementation method are provided. The .sup.14C testing bottle includes a pressure-bearing shell and a sample bin positioned in the pressure-bearing shell. A cavity is arranged in the sample bin and the .sup.14C testing bottle is provided with an injection port connected to the cavity. The sample bin may diffuse the light produced in the cavity and at least part of the sample bin is transparent. An optical fiber channel is set on the pressure-bearing shell. One end of the optical fiber channel is connected with an external scintillation counter, and the other end of the optical fiber channel is connected with the transparent part of the sample bin. The .sup.14C testing bottle may measure the .sup.14C content in the carbon dioxide sample rapidly.

A radioactive gas assay system comprises a scintillation cell production assembly, a detector assembly, a computer assembly, and a scintillation cell destruction assembly. The scintillation cell production assembly is configured to produce a scintillation cell comprising a glass scintillator shell containing a volume of radioactive gas. The detector assembly is configured to receive the scintillation cell and to detect photons emitted thereby. The computer assembly is configured to receive data from the detector assembly to automatically calculate an absolute activity of the volume of radioactive gas of the scintillation cell and radiation detection efficiencies of the detector assembly. The scintillation cell destruction assembly is configured to receive the scintillation cell and to rupture the substantially non-porous glass scintillator shell to release the volume of radioactive gas. A method of assaying a radioactive gas, and a scintillation cell are also described.

A radioactive gas assay system comprises a scintillation cell production assembly, a detector assembly, a computer assembly, and a scintillation cell destruction assembly. The scintillation cell production assembly is configured to produce a scintillation cell comprising a glass scintillator shell containing a volume of radioactive gas. The detector assembly is configured to receive the scintillation cell and to detect photons emitted thereby. The computer assembly is configured to receive data from the detector assembly to automatically calculate an absolute activity of the volume of radioactive gas of the scintillation cell and radiation detection efficiencies of the detector assembly. The scintillation cell destruction assembly is configured to receive the scintillation cell and to rupture the substantially non-porous glass scintillator shell to release the volume of radioactive gas. A method of assaying a radioactive gas, and a scintillation cell are also described.

The invention provides a system for containing irradiated particles, the system having a housing having a closed upstream end and an open downstream end; an axially disposed tunnel extending from the downstream end to the upstream end, wherein longitudinally extending regions of the tunnel define a plurality of threaded surfaces; a sample cup positioned within the tunnel and proximal to the closed upstream end; threaded plugs matingly received by the threaded surfaces so as to provide at least one seal between the sample cup and the atmosphere external of the housing; and a plurality of deformable substrates disposed between the plugs.

A radiation image capturing apparatus is provided. The radiation image capturing apparatus includes an image capturing unit configured to capture a radiation image. The image capturing unit includes a detection element configured to detect radiation. The radiation image capturing apparatus comprises a processor configured to perform, in accordance with an exposure request from a user, a first reset operation of resetting the detection element, and configured to detect an amount of irradiation of the radiation based on a signal from the detection element after the first reset operation.

A radiation image capturing apparatus is provided. The radiation image capturing apparatus includes an image capturing unit configured to capture a radiation image. The image capturing unit includes a detection element configured to detect radiation. The radiation image capturing apparatus comprises a processor configured to perform, in accordance with an exposure request from a user, a first reset operation of resetting the detection element, and configured to detect an amount of irradiation of the radiation based on a signal from the detection element after the first reset operation.