No Brasil, atualmente só há um laboratório de calibração de monitores de radiação de nêutrons, sendo responsável pela guarda e manutenção do padrão brasileiro da fluência de nêutrons, localizado no Laboratório Nacional de Metrologia das Radiações Ionizantes (LNMRI), Rio de Janeiro, no Instituto de Radioproteção e Dosimetria, Comissão Nacional de Energia Nuclear, Rio de Janeiro, com uma demanda grande de serviços com esse tipo de radiação. Com o intuito de descentralizar a oferta de serviços de calibração, surgiu a necessidade da montagem de um segundo Laboratório de Calibração com Nêutrons (LCN), no IPEN. Nas situações práticas envolvendo a calibração de monitores de radiação de nêutrons, um dos problemas principais está relacionado à radiação espalhada, que pode variar dependendo das dimensões do laboratório usado nos procedimentos de calibração. No processo de caracterização do campo de radiação de nêutrons da fonte de 241AmBe, onde foi realizada a avaliação dos espectros, das energias, das taxas de fluência, das taxas de equivalente de dose ambiente [H*(10)] e do coeficiente de conversão de fluência em dose [h*φ(10)] em diferentes posições do LCN, utilizando o feixe completo. A influência da radiação espalhada foi determinada por meio de três técnicas: Métodos de Monte Carlo, de Ajuste Reduzido e do Cone de Sombra. Dos resultados obtidos por meio de simulação e experimentalmente foi possível obter a fração de espalhamento em diferentes distâncias fonte-detector. / In Brazil, there is currently only one calibration laboratory for neutron radiation monitors. It is responsible for the custody and maintenance of the Brazilian neutron fluence standard, located at the Laboratório Nacional de Metrologia das Radiações Ionizantes-LNMRI, Rio de Janeiro, at the Instituto de Radioproteção e Dosimetria, Comissão Nacional de Energia Nuclear, with a great demand of services with this type of radiation. In order to decentralize the calibration service offer, it was necessary to set up a second Neutron Calibration Laboratory (LCN), at IPEN. In practical situations involving the calibration of neutron radiation monitors, one of the main problems is related to scattered radiation, which may vary depending on the size of the laboratory used for the calibration procedures. In the process of characterization of the neutron radiation field of the 241AmBe source, the spectra, the energies, the fluence rate, the ambient dose equivalent rate and the conversion coefficient of fluence in dose at different positions of the LCN, were evaluated using the complete beam. The influence of the scattered radiation was determined by three techniques: Monte Carlo Method, the Reduced Adjustment Method and the Shade Cone Method. From the results obtained through simulation and experimentally, it was possible to obtain the scattering fraction at different source-detector distances.

No Brasil, atualmente só há um laboratório de calibração de monitores de radiação de nêutrons, sendo responsável pela guarda e manutenção do padrão brasileiro da fluência de nêutrons, localizado no Laboratório Nacional de Metrologia das Radiações Ionizantes (LNMRI), Rio de Janeiro, no Instituto de Radioproteção e Dosimetria, Comissão Nacional de Energia Nuclear, Rio de Janeiro, com uma demanda grande de serviços com esse tipo de radiação. Com o intuito de descentralizar a oferta de serviços de calibração, surgiu a necessidade da montagem de um segundo Laboratório de Calibração com Nêutrons (LCN), no IPEN. Nas situações práticas envolvendo a calibração de monitores de radiação de nêutrons, um dos problemas principais está relacionado à radiação espalhada, que pode variar dependendo das dimensões do laboratório usado nos procedimentos de calibração. No processo de caracterização do campo de radiação de nêutrons da fonte de 241AmBe, onde foi realizada a avaliação dos espectros, das energias, das taxas de fluência, das taxas de equivalente de dose ambiente [H*(10)] e do coeficiente de conversão de fluência em dose [h*φ(10)] em diferentes posições do LCN, utilizando o feixe completo. A influência da radiação espalhada foi determinada por meio de três técnicas: Métodos de Monte Carlo, de Ajuste Reduzido e do Cone de Sombra. Dos resultados obtidos por meio de simulação e experimentalmente foi possível obter a fração de espalhamento em diferentes distâncias fonte-detector. / In Brazil, there is currently only one calibration laboratory for neutron radiation monitors. It is responsible for the custody and maintenance of the Brazilian neutron fluence standard, located at the Laboratório Nacional de Metrologia das Radiações Ionizantes-LNMRI, Rio de Janeiro, at the Instituto de Radioproteção e Dosimetria, Comissão Nacional de Energia Nuclear, with a great demand of services with this type of radiation. In order to decentralize the calibration service offer, it was necessary to set up a second Neutron Calibration Laboratory (LCN), at IPEN. In practical situations involving the calibration of neutron radiation monitors, one of the main problems is related to scattered radiation, which may vary depending on the size of the laboratory used for the calibration procedures. In the process of characterization of the neutron radiation field of the 241AmBe source, the spectra, the energies, the fluence rate, the ambient dose equivalent rate and the conversion coefficient of fluence in dose at different positions of the LCN, were evaluated using the complete beam. The influence of the scattered radiation was determined by three techniques: Monte Carlo Method, the Reduced Adjustment Method and the Shade Cone Method. From the results obtained through simulation and experimentally, it was possible to obtain the scattering fraction at different source-detector distances.

Objectives: To evaluate the influence of five different displays on the diagnosis of artificial caries-like lesions on restored and unrestored tooth surfaces. Materials & Methods: 60 extracted human teeth (30 premolars and 30 molars) were selected. All molars had class II cavities prepared and restored. Half of the premolars and molars were randomly selected and a 7mm² area was exposed to a demineralizing solution for 120 days. Phantoms with four teeth (two premolars and two molars) were created. Periapical radiographs were obtained on RVG 6100 digital sensor (Kodak Dental Systems, New York, USA). The images were evaluated under subdued lighting on five viewing displays (Barco MDNC-3321, NEC Wide, Apple iPad Pro, Microsoft Surface Pro 4 and Dell flat panel monitor) by three observers using a five-point rating scale. Sensitivity (Sn), specificity (Sp), accuracy (Ac) and Receiver Operating Characteristic (ROC) curves and their areas under the curves (AUC) were calculated and compared by Analysis of variance and post-hoc Tukey test. Intraobserver and interobserver agreement were accomplished after a three month interval observational.. The observer agreement was evaluated with the Cohen’s kappa test. Results: Even though the tablets slightly improved accuracy over the medical monitors, there was no statistically significant difference in sensitivity, specificity, accuracy or AUC among the five monitors when the same tooth group was considered (p< 0.05) with the exception of the iPad Pro which had a specificity p-value of 0.014 when comparing the two materials within the iPad Pro. Conclusion: There is no perceivable disadvantage to utilizing a higher resolution tablet viewing platform for plane images. No advantage to the medical grade monitors over the tablets or the consumer monitor. Both tablets improved detection accuracy on the unrestored premolars. However further evaluation especially in a clinical lighting setting is warranted to evaluate a displays impact on observer performance within common clinical practice lighting parameters.

In the hectic world of an IT helpdesk with an ever increasing number of applications and tasks on the go, managing the intricacies of how to navigate these is a cause of frustration for helpdesk workers. I had noticed while working on a helpdesk that the workspace area - particularly the monitor setups that IT helpdesk workers have to use - makes doing their job difficult. The number of applications open, the number of tasks on the go at once and the added pressure of customer contact, all call for applications and data to be accessed quickly - but the set up of the users workspace generally does not allow for this. The main objective of this research is to compare the difference between the use of a single screen, a dual screen and the new Multi-Layer Display (MLD) and the complications of having multiple applications and multiple monitors operating at one time for IT Helpdesk Workers. This research looked at how the users' monitor setup influenced the performance, efficiency, satisfaction, ergonomics and learning of the participants.The research showed that there was a clear dislike of the current set up of single screens; all participants felt that the single screen setup limited what they could do at once and it rated the least favourite of all. The dual and MLD screens showed positive outcomes for increasing multi-tasking abilities and raising users' perceived performance and satisfaction levels. The added screen real estate of both the dual and MLD over the single screen meant that users consistently had more information available to them 7which enabled them to complete tasks quicker, monitor other applications for incoming jobs, easily transfer data from one application to another and multi-task more effectively. While there were some minor ergonomic concerns and learning difficulties with the unique features and utilities of the both the dual and MLD monitors, participants still preferred to use these setups over the single screen.

After introducing the concept of multiple monitors, which is a computer system with a physically partitioned but virtually contiguous display space (a single computer with many monitors attached), we discuss open Human-Computer Interaction multiple-monitor research areas including window management. We argue to conduct a high-level study of window management practices and a low-level study specifically comparing single-monitor and multiple-monitor window management practices. When combined with other field work on multiple monitors, the studies suggest that there is an increasingly crucial distinction between input focus (where the active window is) and user focus (where the user is actually looking on-screen) since multiple monitors encourage users to display reference information in non-active windows to aid interaction in the active window. To further explore this distinction we constructed three tools: Snip; Snap; and Mudibo. We deployed Snip and Snap in a field study, finding that participants used Snip in many of the ways that we expected though Snap did not appear to be as useful. Results from our follow-up laboratory-based study indicated that Snip can provide multiple-monitor users with dramatic time savings for referencing the snipped windows as compared to regular, overlapping windows. A laboratory-based study of Mudibo, a dialog box placement interface, provided further motivation of the tool and uncovered key interface improvements necessary to make Mudibo suitable for everyday multiple-monitor screen interaction. The findings support the original conclusion about the initial field work, namely that understanding the potentially larger gap between input focus and user focus necessitates appropriately targeted user interface development and evaluation.

The dissolution of the Soviet Union coupled with the growing sophistication of international terror organizations has brought about a desire to ensure that a sound infrastructure exists to interdict smuggled nuclear material prior to leaving its country of origin. To combat the threat of nuclear trafficking, radiation portal monitors (RPMs) are deployed around the world to intercept illicit material while in transit by passively detecting gamma and neutron radiation. Portal monitors in some locations have reported abnormally high gamma background count rates. The higher background data has been attributed, in part, to the concrete surrounding the portal monitors. Higher background can ultimately lead to more material passing through the RPMs undetected. This work is focused on understanding the influence of the concrete surrounding the monitors on the total gamma ray background for the system. This research employed a combination of destructive and nondestructive analytical techniques with computer simulations to form a model that may be adapted to any RPM configuration. Six samples were taken from three different composition concrete slabs. The natural radiologcal background of these samples was determined using a high-purity germanium (HPGe) detector in conjunction with the Canberra In-Situ Object Counting System (ISOCS™) and Genie™ 2000 software packages. The composition of each sample was determined using thermal and fast neutron activation analysis (NAA) techniques. The results from these experiments were incorporated into a Monte Carlo N-Particle (MNCP) photon transport simulation to determine the expected gamma ray count rate in the RPM due to the concrete. The results indicate that a quantitative estimate may be possible if the experimental conditions are optimized to eliminate sources of uncertainty. Comparisons of actual and simulated count rate data for 137Cs check sources showed that the model was accurate to within 15%. A comparison of estimated and simulated count rates in one concrete slab showed that the model was accurate to within 4%. Subsequent sensitivity analysis showed that if the elemental concentrations are well known, the carbon and hydrogen content could be easily estimated. Another sensitivity analysis revealed that the small fluctuations in density have a minimal impact on the gamma count rate. The research described by this thesis provides a method by which RPM end users may quantitatively estimate the expected gamma background from concrete foundations beneath the systems. This allows customers to adjust alarm thresholds to compensate for the elevated background due to the concrete, thereby increasing the probability of intercepting illicit radiological and nuclear material.

Der Reaktordruckbehälter (RDB) zählt zu den nicht auswechselbaren Komponenten eines Kernkraftwerkes (KKW). Durch die hohen Neutronen- und Gammaflüsse ist er beschleunigten Alterungsprozessen unterworfen, welche die Lebensdauer eines KKW bestimmen könnten. So haben neben der chemischen Zusammensetzung des RDB-Stahls vor allem die Strahlungsparameter (Neutronen- und Gammafluenzen und deren Spektren) Auswirkungen auf die Versprödungseigenschaften des RDB. Für einen sicheren Betrieb eines KKW ist es daher sehr wichtig, die mögliche Änderung des Materialzustandes vom RDB im Voraus bewerten zu können. Die sogenannten Voreilprobenprogramme gehören deshalb zu den wichtigsten Überwachungsmaßnahmen im KKW. Mit ihnen kann die Restlebensdauer des RDB realistisch und zuverlässig beurteilt werden. In dieser Arbeit werden, neben der Bestimmung der Fluenzen an sich, auch Auswirkungen auf den Teilchenfluss in den Voreilproben, wie zum Beispiel die verschiedenen geometrischen Positionen, untersucht. Damit können mögliche Unsicherheiten bei der Bestimmung der realen Fluenzwerte abgeschätzt werden. Die Berechnungen wurden sowohl mit dem Code TRAMO als auch mit dem Code DORT durchgeführt. Die berechneten Ergebnisse wurden an Aktivierungsmonitoren, die an der RDBAußenoberfläche des KKW Kola, Unit 3 (WWER-440/213), bestrahlt wurden, überprüft. Hauptsächlich kamen Aktivierungsmonitore mit den Reaktionen 54Fe(n,p)54Mn und 58Ni(n,p)58Co zum Einsatz. Die Aktivitätsmessungen wurden vom russischen Partner, dem „Scientific and Engineering Centre for Nuclear and Radiation Safety“ (SEC NRS) durchgeführt. Es konnte gute Übereinstimmung sowohl zwischen den deterministischen und den stochastischen Berechnungsergebnissen als auch zwischen den berechneten und gemessenen Ergebnissen erzielt werden. Die durchschnittliche Differenz zwischen gemessenen und berechneten Werten betrug nur 5%. Ein Einfluss der Bestrahlungskanäle und der Versteifungsrippen der Kernumfassung auf die Monitoraktivität konnte festgestellt werden. Für die Voreilproben im Bereich des Flussmaximums wurden für den Neutronenfluss E> 0.5 MeV ein Mittelwert von rund 2.45*1012 Neutronen/cm2 berechnet. Dabei können die Unterschiede in Abhängigkeit von der Ausrichtung der Proben zum Reaktorkern bis zu 20% betragen. Abweichungen bis zu 10% können durch die Änderung der Position der Bestrahlungskapseln im Kanal entstehen. Auf Basis dieser Rechnungen wurden die Voreilfaktoren der Bestrahlungsproben bestimmt. Bei mittleren Zykluslängen würde die „End of Life“-Fluenz in den Bestrahlungsproben bereits nach 2 Jahren erreicht werden. Der berechnete maximale Gammafluss beträgt rund 3.4*1012 g/cm2s für E > 1.0 MeV und rund 8.4*1012 g/cm2s für E > 0.5 MeV, wobei der größte Anteil des Flusses (rund 97%) aus Neutronenreaktionen stammt. Damit sind die Gammaflüsse in den Proben zwei bis drei Mal so groß wie die der Neutronen. Trotzdem spielt die Materialschädigung durch die Gammastrahlung eine untergeordnete Rolle, da die DPAQuerschnitte (displacement per atom) von Gammas um etwa zwei bis drei Größenordnungen kleiner sind. Des Weiteren wurde untersucht, ob mögliche Ausheilprozesse durch zu hohe Temperaturen in den Bestrahlungsproben stattfinden könnten. Zu diesem Zweck wurde der Energieeintrag in den Bestrahlungsproben basierend auf den berechneten Teilchenflüssen bestimmt und mit einfachen thermohydraulischen Modellen die mögliche Aufheizung ermittelt. Eine Temperaturerhöhung von rund 20 K wurde mit einem konservativen Ansatz berechnet. Unter vergleichsweise realistischen Bedingungen reduzierte sich die Aufheizung auf unter 5 K. / Reactor pressure vessels (RPV) are non-restorable equipment and their lifetime may restrict the nuclear power plant-life as a whole. Surveillance specimen programs for RPV materials are among the most important measures of in-service inspection pro-grams that are necessary for realistic and reliable assessment of the RPV residual lifetime. In addition to the chemical composition of the RPV steel, the radiation pa-rameters (neutron and gamma fluences and spectra) have the most important impact on the RPV embrittlement characteristics. In this work, different geometric positions which have influence on the radiation conditions of the samples are investigated. Thus, the uncertainties can be determined in the fluence values of surveillance specimens. The fluence calculations were carried out by the codes TRAMO and DORT. This study was accompanied by ex-vessel neutron dosimetry experiments at Kola NPP, Unit 3 (VVER-440/213), which provide the basis for validation of calculated neutron fluences. The main neutron-activation monitoring reactions were 54Fe(n,p)54Mn and 58Ni(n,p)58Co. The activity measurements were carried out by “Scientific and Engineering Centre for Nuclear and Radiation Safety (SEC NRS). Good agreement between the deterministic and stochastic calculation results as well as between the calculations and the ex-vessel measurements was found. The aver-age difference between measured and calculated values is 5%. The influence of the channels for surveillance specimens and the shielding effect of a baffle rib on the monitors and on the Monte-Carlo calculated results was studied. For the surveillance specimens in the maximum of the flux, an average flux of around 2.45 * 1012 neutrons/cm2 was calculated for the neutron flux E> 0.5 MeV. The differences in the surveillance specimens could be up to 20% depending on the direction to the core. Discrepancies up to 10% can be caused by the change of the position of the capsules in the irradiation channel. Based on these calculations the lead factor of specimens was determined. The maximum fluence of RPV may be achieved after two cycles. The calculated maximum gamma flux is around 3.4 * 1012 g/cm2s for E> 1.0 MeV and around 8.4 * 1012 g/cm2s for E> 0.5 MeV, with the largest part of the flux (around 97%) from the neutron reactions. The gamma fluxes in the surveillance specimens are two to three times bigger than the neutron fluxes. Nevertheless, the material damage by the gamma radiation is very small, because the dpa (displacement per atom) cross sections of gamma rays are about two to three orders of magnitude smaller. In order to exclude the possibility of healing effects of the samples due to excessive temperatures, the heat release in the surveillance specimens was determined based on the calculated gamma fluences. The analytic treatment of the heat conduction equation and simplified SS geometries were adopted to calculate the range of tem-peratures to be expected. The temperature increase of 20 K above the inlet coolant temperature was estimated using a conservative approach. Under comparatively re-alistic conditions, the heating was reduced to less than 5 K.

No description available.

In the hectic world of an IT helpdesk with an ever increasing number of applications and tasks on the go, managing the intricacies of how to navigate these is a cause of frustration for helpdesk workers. I had noticed while working on a helpdesk that the workspace area - particularly the monitor setups that IT helpdesk workers have to use - makes doing their job difficult. The number of applications open, the number of tasks on the go at once and the added pressure of customer contact, all call for applications and data to be accessed quickly - but the set up of the users workspace generally does not allow for this. The main objective of this research is to compare the difference between the use of a single screen, a dual screen and the new Multi-Layer Display (MLD) and the complications of having multiple applications and multiple monitors operating at one time for IT Helpdesk Workers. This research looked at how the users' monitor setup influenced the performance, efficiency, satisfaction, ergonomics and learning of the participants.The research showed that there was a clear dislike of the current set up of single screens; all participants felt that the single screen setup limited what they could do at once and it rated the least favourite of all. The dual and MLD screens showed positive outcomes for increasing multi-tasking abilities and raising users' perceived performance and satisfaction levels. The added screen real estate of both the dual and MLD over the single screen meant that users consistently had more information available to them 7which enabled them to complete tasks quicker, monitor other applications for incoming jobs, easily transfer data from one application to another and multi-task more effectively. While there were some minor ergonomic concerns and learning difficulties with the unique features and utilities of the both the dual and MLD monitors, participants still preferred to use these setups over the single screen.

Thesis (Ph. D.)--Ohio State University, 2006. / Title from first page of PDF file. Includes bibliographical references (p. 197-203).