Abstract:
Disclosed is a dose measuring device for the measurement of a radiation dose which comprises a radiation-sensitive measuring film and a base body, wherein the measuring film is wound onto the base body in some areas. Furthermore, a measurement method using such a dose measuring device is disclosed to determine the radiation dose applied during the pasteurization and/or sterilization of particulate material.
Abstract:
A hand-held portable radiation detection device, such as a radiation isotopic identification device (RIID), is integrated with a personal digital assistant device (PDA), such as a smart phone, to provide improved data processing capability and user interface. The hand-held portable radiation detection device includes a mounting unit for holding the PDA, in which at least one function of the PDA may be controlled by a plurality of buttons provided on an outer casing of the radiation detection device.
Abstract:
Apparatus, systems, and methods for nuclear radiation cleanup and uranium prospecting include the steps of identifying an area; collecting samples; sample preparation; identification, assay, and analysis; and relating the samples to the area.
Abstract:
Apparatus, systems, and methods for nuclear radiation cleanup and uranium prospecting include the steps of identifying an area; collecting samples; sample preparation; identification, assay, and analysis; and relating the samples to the area.
Abstract:
A system for assaying an eluate for Technetium-99m and Molybdenum-99 content includes an inner ionization chamber including a well configured to receive the eluate, an outer ionization chamber concentric with the inner ionization chamber, and attenuating material positioned between the inner and outer ionization chambers. A computing device is configured to determine a Technetium-99m content of the eluate based on a first current measured in the inner ionization chamber, and determine a Molybdenum-99 content of the eluate based on at least a second current measured in the outer ionization chamber.
Abstract:
A nuclear reactor fuel integrity monitor includes: a γ-ray detector which detects γ-ray of a specific radionuclide of a subject measurement medium of a nuclear reactor; a sample container which retains the subject measurement medium therein and surrounds the circumference of the γ-ray detector; and a measurement control device which performs a control so that a predetermined amount of the subject measurement medium is introduced into the sample container and calculates a concentration of the specific radionuclide from γ-ray data per each unit time detected by the γ-ray detector and a volume of the subject measurement medium introduced into the sample container.
Abstract:
A detector system measures radioactive material. A fluid path receives at least one aliquot of radiopharmaceutical. The fluid path locates the aliquot within a positioner formed with a concave configuration. A detector is located at an axial distance from the concave surface and determines the level of radioactivity of the aliquot. Alternatively, the fluid path may be less concave and a variable attenuator may be placed between the fluid path and detector. The variable attenuator may have a concavity that is based on the concavity of the fluid path so that the detector's ability to read the radioactivity is optimized. A method for forming an aliquot of radiopharmaceutical in a concave fluid passage. Positioning a detector located a distance from the concave surface to optimize reading spectral energy of the aliquot and activity is determining activity regardless of the position of the aliquot in the passage.
Abstract:
Cell, whose interior (3) is filled with liquid, whose radioactivity is measured by a scintillator or other detector install thereon. The invention consists of equipping the cell with rinsing means in order to wash the cell side wall (2) and the sealing or blanking plate (13) with respect to impurities deposited thereon and interfering with the measurement as a result of their natural radioactivity. Blowing means are provided above the free surface of the radioactive liquid in order to oppose its vaporization, which would produce other deposits.
Abstract:
Apparatus for measuring the .alpha. activity of a solution and used for determining the plutonium concentration of a solution sampled from an irradiated nuclear fuel reprocessing installation and which comprises a rotary drum (20), which samples a film of solution in a vessel (20), in order to place it in front of a measuring probe (22). Between the probe (22) and the drum (20) is positioned a sealing disk (40) having three positions, which has an effective measuring region (48), a measuring chain quality checking region and a blank measuring region. In order to avoid a solution deposit by condensation on the disk (40) or on the end of the probe (22), a protective gas injection system (49) having passages traversing the vessel cover (16), scavenges the upper face of the sealing disk at three locations corresponding to the three active regions of the latter. A substantially uniform distribution of the gas flow between said three locations is ensured. The protective gas is then sucked in by a tube (122).
Abstract:
An automatic radioisotope filling apparatus which includes a radioisotope vial containing a radioisotope solution, a saline vial containing a physiological saline solution and a plurality of label vials containing a drug into which a predetermined amount of the radioisotope solution or the physiological saline solution is to be filled automatically. A required amount of the radioisotope solution or the physiological saline solution is automatically metered and automatically filled into each label vial and consequently the radiation exposure of the operator of the apparatus is minimized.