Title from PDF of title page. / Document formatted into pages; contains 64 pages. / Thesis (M.E.E.)--University of South Florida, 2003. / Includes bibliographical references. / Text (Electronic thesis) in PDF format. / ABSTRACT: The ability of Mercuric Iodide (HgI2) to function as a highly efficient radiation detector at room temperature has generated great interest and has triggered further studies on this difficult material. This property is expected to enable significant enhancements to a far-ranging variety of applications and systems. HgI2 devices have shown superior performance at room temperature compared to elemental Si or Ge devices, which require to be cooled down to liquid nitrogen temperature when used as nuclear radiation detectors. While substantial studies have been conducted on single crystal HgI2, polycrystalline HgI2 remains a comparatively less studied form of this material. The primary use of HgI2 is as a direct radiation detector. It can also be used in applications with a scintillator intermediate to generate visible light from incident nuclear radiation. Hence its response to visible light can be used to study the electronic properties of HgI2 polycrystalline films. / ABSTRACT: The films are deposited on TEC-15 LOF glass with a Tin Oxide(Sn02) coating which acts as the growth surface. It also acts as the front contact with Palladium (Pd) being the back contact. Wire leads are attached to the palladium for electrical contact. The deposited films are circular in shape with a diameter of 2.5cm with thickness ranging from 50 to 600ìm. A maximum of 7 devices are contacted at various points on every film. For the measurements documented in this thesis, a tungsten-halogen lamp and an Oriel 1/4m grating monochromator are used as a light source. The incident flux on the sample is determined using a Si photodiode as reference. Device performance for both single crystal as well as polycrystalline films is documented. We have attempted to identify a set of optimum growth parameters using these measurements. / ABSTRACT: For a film to be considered favorably, not only should the individual devices show high quantum efficiencies and low dark currents, but the response of all devices on the same film should be uniform. A number of films are studied and the optimum film deposition conditions are commented upon. A powerful semiconductor device simulation tool, MEDICItm, is used to simulate the photoresponse of these films. The simulations are compared to the measurements and the transport and light absorption parameters of the polycrystalline films are determined. / System requirements: World Wide Web browser and PDF reader. / Mode of access: World Wide Web.

In dem Bericht werden Strahlungsquelle aufgeführt, die den Untergrund bei der Messung geringer Radioaktivitäten verursachen und dargestellt wie zur Unterdrückung der kosmischen Strahlung Laboratorien untertägig eingerichtet werden und wie durch Koinzidenz und Antikoinzidenzverfahren der verbleibende Untergrund weiter reduziert werden kann. / The radiation sources are described, which causes the background at the measurement of low radioactivities. To reduce the influence of cosmic rays counting devises are installed in underground laboratories. The remaining background may be further reduced by coincidence and anti-coincidence methods.

Radon is a naturally occurring radioactive element in the 238U decay series that is found in high concentrations in certain geological formations such as Caves. Exposure to high concentrations of radon has been positively linked to the incidence<br /> of lung cancer. This study used Electret ion chambers and the RAD7 continuous radon monitor to measure radon concentrations in the Cango Caves in the Western Cape Province, South Africa. Measurements were taken during summer i.e. February 2004 and March 2005. The results for the radon activity concentrations range from the minimum of<br /> about 800 Bq.m-3 to a maximum of 2600 Bq.m-3. The two techniques give very similar results, though the Electret ion chamber results appear to be consistently higher by a few percent where measurements were taken at the same locations. A<br /> mathematical model has been developed to investigate the radon concentrations in the Cave. Diffusion and ventilation have been considered as mechanisms for explaining the distribution of radon concentrations. The ventilation rate in the Cave has been estimated under certain assumptions, and it is found to be about 7 &times / 10&minus / 6 s&minus / 1 for the Van Zyl hall which is the first large chamber in the Cave. The radon concentration increases as one goes deeper into the Cave, but then becomes fairly constant for the deeper parts. The annual effective dose that the guides are exposed to in the Cave as a result of the radon concentrations, depends strongly on the time that they spend in the Cave and in which, halls they spend most of their time in the Cave. The initial results indicate an annual effective dose of 4-10 mSv, but this needs to be further investigated.

Radioactive xenon gas is a fission product released in the detonation of nuclear devices that can be detected in atmospheric samples far from the detonation site. In order to improve the capabilities of radioxenon detection systems, this work produces [beta-gamma] coincidence spectra of individual isotopes of radioxenon. Previous methods of radioxenon production consisted of the removal of mixed isotope samples of radioxenon gas released from fission of contained fissile materials such as ²³⁵U. In order to produce individual samples of the gas, isotopically enriched stable xenon gas is irradiated with neutrons. The detection of the individual isotopes is also modeled using Monte Carlo simulations to produce spectra. The experiment shows that samples of [superscript 131m]Xe, ¹³³Xe, and ¹³⁵Xe with a purity greater than 99% can be produced, and that a sample of [superscript 133m]Xe can be produced with a relatively low amount of ¹³³Xe background. These spectra are compared to models and used as essential library data for the Spectral Deconvolution Analysis Tool (SDAT) to analyze atmospheric samples of radioxenon for evidence of nuclear events. / text

Radon is a naturally occurring radioactive element in the 238U decay series that is found in high concentrations in certain geological formations such as Caves. Exposure to high concentrations of radon has been positively linked to the incidence<br /> of lung cancer. This study used Electret ion chambers and the RAD7 continuous radon monitor to measure radon concentrations in the Cango Caves in the Western Cape Province, South Africa. Measurements were taken during summer i.e. February 2004 and March 2005. The results for the radon activity concentrations range from the minimum of<br /> about 800 Bq.m-3 to a maximum of 2600 Bq.m-3. The two techniques give very similar results, though the Electret ion chamber results appear to be consistently higher by a few percent where measurements were taken at the same locations. A<br /> mathematical model has been developed to investigate the radon concentrations in the Cave. Diffusion and ventilation have been considered as mechanisms for explaining the distribution of radon concentrations. The ventilation rate in the Cave has been estimated under certain assumptions, and it is found to be about 7 &times / 10&minus / 6 s&minus / 1 for the Van Zyl hall which is the first large chamber in the Cave. The radon concentration increases as one goes deeper into the Cave, but then becomes fairly constant for the deeper parts. The annual effective dose that the guides are exposed to in the Cave as a result of the radon concentrations, depends strongly on the time that they spend in the Cave and in which, halls they spend most of their time in the Cave. The initial results indicate an annual effective dose of 4-10 mSv, but this needs to be further investigated.

La dosimétrie en réacteur permet de déterminer la fluence neutronique reçue pendant une irradiation et d’en caractériser le spectre (distribution énergétique des neutrons). Cette technique s’appuie sur la mesure de l’activité de dosimètres irradiés, constitués de métaux purs ou d’alliages. La mesure d’activité de ces échantillons est réalisée par spectrométrie gamma et X sur des rayonnements de faibles énergies (< 100 keV) et s’appuie actuellement sur un dosimètre étalon adapté et validé spécifiquement pour les conditions de mesure. Le but de la thèse est de s’affranchir de cette étape et de pouvoir mesurer directement l’activité des dosimètres. L’étude a concerné spécifiquement les dosimètres en niobium et en rhodium qui sont utilisés pour caractériser la signature des neutrons d’énergie autour de 1 MeV. Ils sont respectivement activés en Nb-93m et 1Rh-103m. Ces deux radionucléides se désintègrent par une transition gamma en émettant principalement des photons XK d’énergie autour de 20 keV, sur lesquels s’appuie la mesure d’activité en spectrométrie. Or, du fait de leur faible énergie, ces rayonnements présentent de nombreuses difficultés pour être analysés avec précision. Les différents paramètres nécessaires à la quantification de l’activité des dosimètres, avec une incertitude relative de l’ordre de 2 %, ont été étudiés en détails. Les travaux ont d’abord porté sur l’étalonnage en rendement des détecteurs au germanium hyper-pur (GeHP) dans la gamme d’énergie comprise entre 11 keV et 150 keV. Ceci constitue une étape cruciale dans la détermination de l’activité et s’avère délicate dans la gamme d’énergie considérée. L’approche expérimentale, utilisant des sources ponctuelles étalons, a été couplée à des modélisations semi-empiriques et à des simulations des interactions rayonnements-matière par des méthodes Monte Carlo (PENELOPE et GEANT4). Ces dernières ont permis d’approfondir l’étude du phénomène de diffusion des photons en basse énergie, aux alentours de 20 keV, qui interfère avec les pics d’absorption totale dans les spectres et perturbe leur analyse. Dans un second temps, les simulations de Monte Carlo ont également été utilisées pour établir les facteurs de corrections nécessaires à la mesure des dosimètres : auto-absorption du rayonnement dans le matériau et changement de géométrie entre les conditions d’étalonnage (source ponctuelle) et les conditions de mesure (échantillon métallique massif). Le phénomène de fluorescence lié à la présence d’impuretés (dans le matériau du dosimètre ou créées lors de l’irradiation en réacteur) a été étudié et les facteurs de corrections à appliquer pour en tenir compte ont été établis. Les données du schéma de désintégration, en particulier les intensités d'émission des rayons X, sont les principales composantes de l'incertitude sur la valeur d'activité des dosimètres. Les intensités d'émission X font rarement l'objet de mesures expérimentales, le plus souvent, leurs valeurs découlent du schéma de désintégration et des données fondamentales nucléaires et atomiques de l'élément tels les coefficients de conversion interne et le rendement de fluorescence. Plusieurs expériences ont été menées pour fournir de nouvelles données expérimentales. Les coefficients d’atténuation massique et les rendements de fluorescence K du niobium et du rhodium ont été déterminés en utilisant un rayonnement photonique monochromatique sur le synchrotron SOLEIL. Les intensités d’émission du Rh-103m ont été mesurées suivant deux approches, l’une à partir de rhodium activé au réacteur ISIS et l’autre à partir d’une solution de palladium-103. Toutes ces nouvelles valeurs sont comparées aux données publiées et le schéma de désintégration du Rh-103m est discuté. / Reactor dosimetry is used to determine the neutron fluence during an irradiation and to characterize its spectrum (neutron energy distribution). This technique is based on the analysis of the activity of irradiated dosimeters, made of pure metals or alloys. The activity measurement of these samples is performed by gamma and/or X-ray spectrometry and is currently based on specific standard dosimeters, validated for the measurement conditions. The goal of the thesis is to avoid this calibration step and to be able to directly measure the activity of the sample. The study focused specifically on niobium and rhodium dosimeters which are used to characterize neutrons in the energy range around 1 MeV. Their activation produces 93mNb and 103mRh, respectively. These two radionuclides decay through an isomeric gamma transition, emitting mainly K X-rays with energies around 20 keV, on which the spectrometric activity measurement is based. However, owing to their low energy, these X-rays are particularly difficult to measure accurately. The various parameters required to determine the activity of the dosimeters, with a relative standard uncertainty of around 2%, were studied in detail. The work initially focused on the calibration of hyper-pure germanium (HPGe) detectors in the energy range between 11 keV and 150 keV. This is a crucial step in determining the activity of a radionuclide sample and is difficult to achieve in the energy range of interest. The experimental approach, using standard point sources, was coupled with semi-empirical modelling and simulations of radiation-matter interactions by Monte Carlo methods (PENELOPE and GEANT4). These methods have made it possible to study in detail the photons scattering at low energy, around 20 keV, which interferes with the full-energy peaks in the spectra and disturbs their analysis. In a second step, Monte Carlo simulations were used to calculate the correction factors needed to derive the dosimeter activity: self-absorption of photons in the dosimeter material and the geometry change between the calibration conditions (point source) and the measurement conditions (solid metal sample). The fluorescence induced by impurities (in the dosimeter material or created during irradiation in the reactor) was studied and the correction factors to be applied were established. Radioactive decay data, particularly photon emission intensities, are the main components of the uncertainty in dosimeter activity results. X-ray emission intensities are rarely measured experimentally and most often their values are calculated from fundamental parameters i.e. internal conversion coefficients and fluorescence yields, and a balanced decay scheme, of the nuclide. Several experiments were designed to provide new experimental data. The mass attenuation coefficients and K fluorescence yields of niobium and rhodium were determined using a monochromatic photon beam at the SOLEIL synchrotron facility. The photon emission intensities of 103mRh were measured using two approaches, one from rhodium activated at the ISIS reactor and the other from a solution of palladium 103. All these new values are compared with previously published data and the decay scheme of 103mRh is discussed.