Durch die Kopplung von Szintillationskristallen an Lichtwellenleiter könnten robuste Messgeräte für die spektroskopitsche Messung von Strahlungsfeldgrößen in Bohrlöchern in Betonstrukturen beim Rückbau von Kernkraftwerken realisiert werden. In dieser Arbeit wurden zwei Prototypen solcher Messgeräte entwickelt, wobei ein auf einem Gadolinium-Aluminium-Gallium-Granat-Szintillationskristall basierendes Messsystem mit einem Kunststofflichtwellenleiter mit hohem Durchmesser aufgrund seiner hohen Zählrate bevorzugt wurde. Mit diesem Messystem konnten spektroskopische Messungen von Gammastrahlung durchgeführt werden. Weiterhin konnte gezeigt werden, dass Kontaminationen einer bestimmten Aktivität bis in einen Abstand von mehreren Zentimetern von der Messsonde im Beton nachweisbar sind. Ein Schätzwert der minimale Messzeit zur Erkennung einer nachweisbaren Kontamination konnte bestimmt werden. Eine hinreichend große, gemessene Ereigniszahl ermöglicht zusätzlich die Bestimmung des Abstands einer radioaktiven, punktförmigen Kontamination eines bekannten Nuklids. Für ein bekanntes Nuklid konnte weiterhin aus der Zählrate ein Schätzwert für die Energiedosis am Ort der Messsonde mithilfe von Referenzmessungen der Dosis mittels Berylliumoxid-Detektoren bestimmt werden.:Inhaltsverzeichnis Abbildungsverzeichnis vii Tabellenverzeichnis ix 1 Einleitung 1 2 Physikalische Grundlagen 3 2.1 Radioaktiver Zerfall 3 2.2 Gröÿen des Strahlungsfelds 3 2.3 Wechselwirkungen von Photonen mit Materie 5 2.4 Lichtentstehung in anorganischen Szintillatoren 8 2.5 Lichtmessung 10 2.6 Pulshöhenverteilungen von Szintillationsdetektoren 12 2.7 Ein ussfaktoren der Lichtausbeute 14 3 Material und Methoden 16 3.1 Aufbau LSO-Sonde und Messungen mit radioaktiven Quellen 16 3.2 Aufbau Lichtkopplung mittels Linse 18 3.3 Aufbau und Versuchsablauf Quarzglaskopplungen 20 3.4 Aufbau GAGG-Sonde 21 3.5 Aufbau des Betonphantoms 24 3.5.1 Dichtebestimmung des Betonphantoms 24 3.6 Messablauf Tiefenkurven in Betonphantom 27 3.7 Datenanalyse mittels Kolmogorv-Smirnov-Test 27 4 Ergebnisse 29 4.1 Spektroskopische Eigenschaften LSO-Sonde 29 4.2 Winkelverteilung austretender Photonen aus Szintillationskristall 33 4.3 Quarzglaskopplung 36 4.4 Spektroskopische Eigenschaften GAGG-Sonde 43 4.5 Vergleich GAGG- und LSO-Sonde 47 4.6 Abstandsabhängigkeit der Zählrate 50 4.7 Abschätzung der maximalen Abschirmdicke von Beton für Kontaminationserkennung 53 4.8 Abschätzung der minimalen Messzeit zur Kontaminationserkennung 56 4.9 Abschirmungsdickenbestimmung mittels Abschirmungsparameter 57 4.10 Bestimmung der Dosis 62 5 Diskussion 64 6 Zusammenfassung 67 / A robust measuring system for spectroscopic measurementes of gamma-ray radiation in boreholes in concrete structures can be built by coupling of a scintillation crystal to a light guide. Two prototypes of such measuring systems are developed one based on a Gadolinium-Aluminium-Gallium-Garnet scintillation crystal with a plastic optical fiber with a high diameter is preferred due to the higher count rate. Spectroscopic measurements of gamma-ray radiation with this measuring system can be performed. It can be shown that contamination of a specific activity can be detected even if they are located in concrete in a distance of several centimeters from the radiation sensor. for the minimal measurement time of 38 s An estimated value to detect a traceable contamination could be determined. If a high number of events can be detected, even the distance between a point like radioaktive source of a known nuclide and the radiation sensor can be determined. An estimated value for the applied dose at the place of the radiation sensor could be determined for a known nuclide with the help of the count rate. Therefore, reference measurements of dose with berylliumoxide detectors were performed.:Inhaltsverzeichnis Abbildungsverzeichnis vii Tabellenverzeichnis ix 1 Einleitung 1 2 Physikalische Grundlagen 3 2.1 Radioaktiver Zerfall 3 2.2 Gröÿen des Strahlungsfelds 3 2.3 Wechselwirkungen von Photonen mit Materie 5 2.4 Lichtentstehung in anorganischen Szintillatoren 8 2.5 Lichtmessung 10 2.6 Pulshöhenverteilungen von Szintillationsdetektoren 12 2.7 Ein ussfaktoren der Lichtausbeute 14 3 Material und Methoden 16 3.1 Aufbau LSO-Sonde und Messungen mit radioaktiven Quellen 16 3.2 Aufbau Lichtkopplung mittels Linse 18 3.3 Aufbau und Versuchsablauf Quarzglaskopplungen 20 3.4 Aufbau GAGG-Sonde 21 3.5 Aufbau des Betonphantoms 24 3.5.1 Dichtebestimmung des Betonphantoms 24 3.6 Messablauf Tiefenkurven in Betonphantom 27 3.7 Datenanalyse mittels Kolmogorv-Smirnov-Test 27 4 Ergebnisse 29 4.1 Spektroskopische Eigenschaften LSO-Sonde 29 4.2 Winkelverteilung austretender Photonen aus Szintillationskristall 33 4.3 Quarzglaskopplung 36 4.4 Spektroskopische Eigenschaften GAGG-Sonde 43 4.5 Vergleich GAGG- und LSO-Sonde 47 4.6 Abstandsabhängigkeit der Zählrate 50 4.7 Abschätzung der maximalen Abschirmdicke von Beton für Kontaminationserkennung 53 4.8 Abschätzung der minimalen Messzeit zur Kontaminationserkennung 56 4.9 Abschirmungsdickenbestimmung mittels Abschirmungsparameter 57 4.10 Bestimmung der Dosis 62 5 Diskussion 64 6 Zusammenfassung 67

[pt] Enfoca-se a análise sísmica de usinas termonucleares sob metodologia no domínio da frequência utilizando-se como modelo, o do prédio do reator da usina Angra 3 e como principal ferramenta o programa de análise de problemas com interação solo-estrutura, SASSI. São avaliadas alternativas para três fases distintas do projeto: geração de sismos artificiais, análise do sistema principal e desenvolvimento de espectros para análise do sistema secundário. Na geração de sismos artificiais, a introdução de critérios de compatibilização complementares ao do espectro de resposta é avaliada considerando-se as consequências sobre as respostas em um ponto da estrutura. No sistema principal, sujeito a excitações sísmicas nas direções horizontal e vertical, comparam-se soluções no domínio do tempo e da freqüência e se reconhece a metodologia na frequência como uma alternativa conveniente à análise no tempo para cálculo de respostas em termos de acelerações , deslocamentos e tensões máximas e de espectros de acelerações. São ainda, desenvolvidos espectros de resposta acoplados para a análise de sistemas secundários segundo sistemática já proposta, para cálculo no domínio do tempo, que comparados com estes, alcançam amplitudes da mesma ordem, porém com tempo de processamento inferior. A metodologia de análise no domínio da frequência apresenta- se como um recurso mais preciso, pois permite a consideração de parâmetros do solo não constantes com a frequência; no que diz respeito ao programa utilizado, mostra-se flexível e acessível. / [en] The seismic analysis of nuclear power plant structures and components is considered to evaluate the convenience to update the brazilian design routine through the use of frequency domain techniques provided by codes such as SASSI. For this purpose one uses a FEM model of a reactor building which has been already analyzed by current techniques in time domain, and comparisons are made with results obtained in the frequency domain, with special attention to the following points: - analysis of the main structures using foundation impedance functions variable with the excitation frequency; - generation of coupled floor response spectra and their application to the analysis of secondary systems; - consideration of complementary criteria based on a minimum seismic spectral density function to generate artificial ground motion accelerograms compatible with a prescribed design response spectrum. As a first step, an exploratory work on the usage of SASSI program is made running a couple of simple examples. In the continuation of the work, a series of runs is made using the above-mentioned structural model under currently prescribed ground motions in the design of brazilian NPP structures. The results are compared with those from previous analyses using different methodologies and some interesting conclusions are brought up. / [es] En el presente trabajo se enfoca el análisis sísmico de plantas termonucleares bajo la metodología en el dominio de la frecuencia utilizando como modelo, el del edificio del reactor de la planta Angra 3 y como principal herramienta el programa de análisis de problemas con interacción suelo-extructura, SASI. Son evaluadas alternativas para tres fases distintas del proyecto: generación de sismos artificiales, análisis del sistema principal y desarrollo de espectros para análisis del sistema secundario. En la generación de sismos artificiales, se evalúa la introducción de criterios de compatibilización complementares al del espectro de respuesta. En el sistema principal, sujeto a excitaciones sísmicas en las direcciones horizontal y vertical, se compararon soluciones en el dominio del tiempo y de la frecuencia. Se reconoce la metodología en la frecuencia como una alternativa conveniente para cálculo de respuestas en términos de aceleraciones, deslocamientos y tensiones máximas y de espectros de aceleraciones. Se desarrollan, además, espectros de respuesta acoplados para el análisis de sistemas secundarios según sistemática ya propuesta, para cálculo en el dominio del tiempo, que comparados con éstes, alcanzan amplitudes de la misma orden, pero con tiempo de procesamiento inferior. La metodología de análisis en el dominio de la frecuencia se presenta como un recurso más preciso, pués permite la consideración de parámetros del suelo no constantes con la frequencia; con respecto al programa utilizado, éste se muestra flexible y accesible.

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The electric utility companies that own and/or operate the nation’s 112 licensed commercial nuclear power reactors are required by federal law to provide emergency information to residents living around those plants in advance of a nuclear plant emergency. This requires the owner/operators to acknowledge certain risks (e.g., radiation, nuclear plant accidents, evacuation, etc.) that face people living near nuclear generating plants. This dissertation critiques the effectiveness of pre-emergency risk communication strategies by nuclear utilities. Specifically, the dissertation demonstrates that certain historic message themes about nuclear power- termed the "nuclear ethic" -have become embedded in the rhetoric of current nuclear risk communication programs and downplay or mask the seriousness of nuclear plant emergencies, thereby contributing to the apparent ineffectiveness of these communication programs. For example, a survey of residents living around four nuclear plants who receive utility risk communication materials found that nearly two-thirds said they would not follow official instructions in a nuclear plant emergency. Such promotional rhetoric and images remain a part of nuclear risk communication programs because agencies which regulate nuclear power delegate their responsibility for pre-emergency risk communication to the utilities operating the plants. Moreover, there is little involvement in pre-emergency nuclear risk communication by state and local governments. This suggests that risk communication serves a latent symbolic role rather than a functional role for both the regulatory agencies and the utilities by making both groups appear to be isomorphic with societal goals of safety and security for a risky technology. The dissertation concludes by suggesting federal regulatory agencies, and specifically the Federal Emergency Management Agency, intensify their vigilance of risk communication planning and take steps to create authentic two-way communication between the nuclear utilities and the public living near the plants. One way this could be done is by establishing local citizens advisory committees to assess utility risk communication programs and suggest improvements that would help bridge the gap between the nuclear industry’s view of nuclear plant risk and that of the public. / Ph. D.

Dedicated sensors are widely used throughout many industries to monitor everyday operations, maintain safety, and report performance characteristics. In order to adopt a more sustainable solution, much research is being applied to self-powered sensing, implementing solutions which harvest wasted ambient energy sources to power these dedicated sensors. The adoption of not only wireless sensor nodes, but also self-powered capabilities in the nuclear energy process is critical as it can address issues in the overall safety and longevity of nuclear power. The removal of wires for data and power transmission can greatly reduce the cost of both installation and upkeep of power plants, while self-powered capabilities can further reduce effort and money spent in replacing batteries, and importantly may enable sensors to work even in losses to power across the plant, increasing plant safety. This thesis outlines three harvesting opportunities in the nuclear energy process from: thermal, vibration, and radiation sources in the main structure of the power plant, and from thermal and radiation energy from spent fuel in dry cask storage. Thermal energy harvesters for the primary and secondary coolant loops are outlined, and experimental analysis done on their longevity in high-radiation environments is discussed. A vibrational energy harvester for large rotating plant machine vibration is designed, prototyped, and tested, and a model is produced to describe its motion and energy output. Finally, an introduction to the design of a gamma radiation and thermal energy harvester for spent nuclear fuel canisters is discussed, and further research steps are suggested. / Master of Science / In this work multiple energy harvesters are investigated aimed at collecting wasted ambient energy to locally power sensor nodes in nuclear power plants, and in spent nuclear fuel canisters. Locally self-powered, wireless sensors can increase safety and reliability throughout the nuclear process. To address this a thermal energy harvester is tested in a radiation rich environment, and its performance before and after irradiation is analyzed. A vibrational energy harvester designed for use on large rotating machinery is discussed, manufactured, and tested, and a mathematical model describing it is produced. Finally, an introduction to harvesting radiation and heat given off from spent nuclear fuel in dry cask canister storage is investigated. Power capabilities for each design are considered, and the impact of such energy harvesting for wireless sensor nodes on the longevity, safety, and reliability of nuclear power plants is discussed.