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1.
Health Phys ; 117(4): 362-377, 2019 10.
Article in English | MEDLINE | ID: mdl-30913060

ABSTRACT

Experiments were performed with 30 11 cm × 42.5 cm × 5.5 cm NaI(Tl) detectors to better understand their positional response. Spectra were collected using 0.02 to 0.15 MBq point sources of Am, Cs, Co, and Ba positioned on lines parallel and perpendicular to the long axis of the crystal along both the narrow and wide detector faces as well as at different distances from them. A greater density of positions was sampled at the ends of the detector, and repeated measurements were made to examine potential gain drifts during the experiment. Spectroscopic peak counts, spectroscopic pulse heights, and net counts were analyzed. Empirical equations were fit to the aforementioned data for each specific source energy as a function of source position. In addition, a Monte Carlo radiation transport code was used to simulate the expected positionally variable response based solely upon radiation absorption. The simulated radiation transport efficiency functions were compared to the experimental data. The effects of the geometric radiation efficiency, the attenuation and scattering of emitted light within the scintillation crystal, and combined effects such as nonuniformity of the photomultiplier tube, photocathode response, and crystal irregularities were then distinguished. Functions describing each effect were derived. The results suggest potential new corrections to data obtained with large scintillation detectors as well as a novel approach to partial positional gamma-ray detection with minimal collimation, given that the energy resolution is within reason for particular photopeaks.


Subject(s)
Computer Simulation , Iodides/chemistry , Monte Carlo Method , Scintillation Counting/instrumentation , Sodium/chemistry , Thallium/chemistry , Equipment Design , Gamma Rays , Humans , Scintillation Counting/methods
2.
Health Phys ; 115(5): 590-599, 2018 11.
Article in English | MEDLINE | ID: mdl-30260849

ABSTRACT

Due to heightened fear surrounding the possibility of future terrorism involving nuclear weapons and radiological dispersive devices, compounded by nonroutine nuclear power plant releases such as from emergencies or accidents, interest in contamination levels of environmental radiation has spiked. This project sought to develop a continuously operational radiation-monitoring system, with graphically visualized data easily accessible to the public. Because this continuing project is housed at a university facility, it bears no connection to perceived political or commercial interests, generally increasing the credibility of the endeavor. Outdoor weather and radiation parameters were gathered by sensors installed on the rooftop of a two-story building. A display and cloud service website was used to project the live data in an understandable format. A correlation was observed between weather and visibly heightened levels of gamma radiation. The goal of this paper is to share and highlight the overall hardware selection and the unique software challenges encountered when developing a robust collection and analysis system, along with the challenges of displaying meteorological and radiological data in a clear and concise fashion.


Subject(s)
Radiation Exposure , Radiation Monitoring , Weather , Access to Information , Data Display , Internet , Radiation Monitoring/methods , Software , Spectrometry, Gamma
3.
Health Phys ; 113(2): 135-142, 2017 08.
Article in English | MEDLINE | ID: mdl-28658059

ABSTRACT

Commercially available gamma-ray imaging spectrometers have been introduced recently and are currently undergoing investigations for various applications in nuclear power plants, environmental management, and medical environments. A Compton imaging gamma-ray spectrometer uses an array of detectors or a single position-sensitive crystal to create planar images of radionuclide distributions. The typical software included with these devices creates images of specific radionuclides using only the counts under their known gamma emission photopeaks. This approach prevents the direct imaging of scattered radiation, which is of interest for many radiation protection applications. In this paper, a technique for imaging radiation scatter or portions of the scatter spectrum is implemented. This involves the creation of a virtual radionuclide in software with peaks placed throughout the backscatter continuum of interest and then imaging that virtual radionuclide in the post-processing software. This technique is used to image the Compton scatter successfully from a polymethyl-methacrylate (PMMA) phantom placed in a Cs irradiator beam. Measured scatter energies were found to be within 15% of the expected values, sufficient to predict scatter behavior and individually measure separate sources of scatter at different angles.


Subject(s)
Biomimetic Materials/chemistry , Cesium/analysis , Gamma Rays , Phantoms, Imaging , Polymethyl Methacrylate/chemistry , Spectrometry, Gamma/instrumentation , Equipment Design , Equipment Failure Analysis , Humans , Radiation Dosage , Reproducibility of Results , Sensitivity and Specificity
4.
Health Phys ; 113(1): 2-12, 2017 07.
Article in English | MEDLINE | ID: mdl-28542006

ABSTRACT

Optically stimulated luminescent (OSL) dosimeters are devices used for measuring doses of ionizing radiation. Signal is stored within an OSL material so that when stimulated with light, light of a specific wavelength is emitted in proportion to the integrated ionizing radiation dose. Each interrogation of the material results in the loss of a small fraction of signal, thus allowing multiple interrogations leading to more accurate measurements of dose. In order to reuse a dosimeter, the residual signals from prior doses must be taken into account and subtracted from current readings, adding uncertainty to any future measurements. To reduce these errors when they become large, it is desirable to completely clear the stored signal or anneal the dosimeter. Traditionally, heating the material has accomplished this. In a commercially available dosimeter badge system, the OSL material Al2O3:C is incorporated into a plastic slide that would melt at the necessary high temperatures, which can reach 900 °C, required for annealing. Fortunately, due to the material's high sensitivity to light, OSLs can be optically annealed instead. In order to do this, an affordable OSL dosimeter annealer was designed with inexpensive, exchangeable blue, green, and white high intensity light-emitting diodes (LEDs). Several dosimeters were repeatedly annealed for recorded intervals and then read out. A single dosimeter was partially annealed through repeated interrogations with the LED array from a commercial reader. The signal loss due to the exposure to each light was analyzed to determine the practicality and efficiency of each color. The rate and extent of signal loss was dependent not only on the spectrum of annealing light but on the initial signal levels as well. These findings suggest that blue LEDs are the most promising for effective and rapid clearing of the OSL material Al2O3:C.


Subject(s)
Lighting/instrumentation , Optically Stimulated Luminescence Dosimetry/instrumentation , Radiation Exposure/analysis , Radioisotopes/analysis , Semiconductors , Equipment Design , Equipment Failure Analysis , Miniaturization , Reproducibility of Results , Sensitivity and Specificity
5.
Health Phys ; 112(3): 237-245, 2017 03.
Article in English | MEDLINE | ID: mdl-28121723

ABSTRACT

Optically-stimulated luminescent dosimeters are capable of being interrogated multiple times post-irradiation. Each interrogation removes a fraction of the signal stored within the optically-stimulated luminescent dosimeter. This signal loss must be corrected to avoid systematic errors in estimating the average signal of a series of optically-stimulated luminescent dosimeter interrogations and requires a minimum number of consecutive readings to determine an average signal that is within a desired accuracy of the true signal with a desired statistical confidence. This paper establishes a technical basis for determining the required number of readings for a particular application of these dosimeters when using certain OSL dosimetry systems.


Subject(s)
Artifacts , Guidelines as Topic , Lighting/standards , Optical Devices/standards , Thermoluminescent Dosimetry/instrumentation , Thermoluminescent Dosimetry/standards , Calibration/standards , Equipment Design , Equipment Failure Analysis , Lighting/instrumentation , Radiation Dosage , Reproducibility of Results , Semiconductors , Sensitivity and Specificity
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