In this work, a new approach to optimize facility layout for toxic release, fire and explosion scenarios is presented. By integrating a risk analysis in the optimization formulation, safer assignments for facility layout and siting have been obtained. Accompanying with the economical concepts used in a plant layout, the new model considers the cost of willing to avoid a fatality, i.e. the potential injury cost due to accidents associated with toxic release near residential areas. For fire and explosion scenarios, the building or equipment damage cost replaces the potential injury cost. Two different approaches have been proposed to optimize the total cost related with layout. In the first phase using continuous-plane approach, the overall problem was initially modeled as a disjunctive program where the coordinates of each facility and cost-related variables are the main unknowns. Then, the convex hull approach was used to reformulate the problem as a Mixed Integer Non-Linear Program (MINLP) that identifies potential layouts by minimizing overall costs. This approach gives the coordinates of each facility in a continuous plane, and estimates for the total length of pipes, the land area, and the selection of safety devices. Finally, the 3D-computational fluid dynamics (CFD) was used to compare the difference between the initial layout and the final layout in order to see how obstacles and separation distances affect the dispersion or overpressures of affected facilities. One of the CFD programs, ANSYS CFX was employed for the dispersion study and Flame Acceleration Simulator (FLACS) for the fires and explosions. In the second phase for fire and explosion scenarios, the study is focused on finding an optimal placement for hazardous facilities and other process plant buildings using the optimization theory and mapping risks on the given land in order to calculate risk in financial terms. The given land is divided in a square grid of which the sides have a certain size and in which each square acquires a risk-score. These risk-scores such as the probability of structural damage are to be multiplied by prices of potential facilities which would be built on the grid. Finally this will give us the financial risk. Accompanying the suggested safety concepts, the new model takes into account construction and operational costs. The overall cost of locations is a function of piping cost, management cost, protection device cost, and financial risk. This approach gives the coordinates of the best location of each facility in a 2-D plane, and estimates the total piping length. Once the final layout is obtained, the CFD code, FLACS is used to simulate and consider obstacle effects in 3-D space. The outcome of this study will be useful in assisting the selection of location for process plant buildings and risk management.

An abnormally high number of explosion quakes were noted during the monitoring effort for the 2007 eruption of Pavlof Volcano on the Alaskan Peninsula. In this study we manually counted the explosion quakes from their characteristic ground-coupled air waves. This study makes an effort at better quantifying the number of explosion quakes and how the characteristic ground-coupled air waves are affected by wind direction and wind speed. Additionally this study investigates how the ground coupled air waves might be used in a monitoring or analysis effort by calculating energy release and gas mass release. Over 3.2x104 quakes were recorded. It was found that wind direction affects the travel time of the air wave by up to 0.7 seconds depending on station location and wind direction. Wind direction and speed, however, are demonstrated not to cause an appreciable difference in ground-coupled air wave frequencies or amplitude ratios. The energy release from the explosions is calculated to be 3.04x1011 J. and the total gas mass (assuming 100% water) released was 729 metric tons. These values are compared to other volcanoes in the literature and found to be somewhat lower. Nevertheless, the tracking of explosion quakes has the potential to become a valuable member of the seismic monitoring arsenal.

A model of the generation and release of fission gas, as well as the total swelling over time, was created. It uses an ideal spherical fuel grain with a time-dependent radius. UO2 and quasi-homogeneous SBR MOX fuels were simulated with this model, and the results were compared to a fixed grain radius model of gaseous swelling. Gaseous swelling and fission gas release were calculated for temperatures from 1600 K to 2200 K. The grain growth of UO2 was found to decrease the time needed to saturate the intergranular boundaries as compared to simple diffusion without grain growth. Small temperatures increased the time required for saturation, as did small rates of grain growth. Gaseous swelling was within the range of values found by experimental data.

In this study we determined the magnitude of plant mediated CH4 emission (flux) in two vegetation types of Carex ramenskii. The objectives of this paper were to quantify the proportion of CH4 emissions from plant mediated flux and the total flux (plant and soil). This information is needed in order to understand how grazing affects plant mediated CH4 flux. In addition, we differentiated between two vegetation morphs, grazed and ungrazed, and determined the plant mediated CH4 flux for vegetation type.  This study was conducted at a field site on the Tutakoke River (61 15’N, 165 30’W) which is located in the coastal region of the Yukon-Kuskokwim Delta. Three replicate plots of the two vegetation morphs of Carex ramenskii were established. Methane flux was measured with a total flux chamber (plant and soil) and a single leaf chamber using a Picarro Cavity Ring-Down Spectroscopy Analyzer (Model G2308, Picarro Inc., Santa Clara, California). Plant density for the two plant types was determined. Temperature measurements were taken and correlated with gas flux. This study found that total net CH4 emissions from Carex ssp. were the same in both vegetation types. This similarity could indicate that plant mediated flux through vegetation is not affected by grazing in the sense that grazing is neither facilitating nor inhibiting plant mediated CH4 flux. The magnitude of plant mediated flux was still greater in the ungrazed meadow type, indicating on both greater facilitation of CH4 flux, and below ground oxygen transport enabling higher rates of CH4 consumption.

Les travaux menés au cours de cette thèse s’inscrivent dans le cadre général de l’évaluation du terme source (relâchement de gaz de fission) en situation incidentelle de type APRP (Accident de Perte de Réfrigérant Primaire). Lors de tels transitoires thermiques, le relâchement de gaz de fission se fait par bouffées successives : une première entre 600°C et 800°C et la seconde à environ 1100°C. Ces travaux de thèse s’intéressent à cette première. Il semblerait que la bouffée à 600-800°C proviendrait du centre de la pastille combustible. L’objectif de cette thèse est d’étudier les mécanismes à l’origine de cette bouffée.Afin de mieux comprendre ces mécanismes, une étude a été menée sur l’ensemble des traitements thermiques réalisés dans la plateforme expérimentale MERARG. L’analyse de cette base de données a révélé 2 points importants : 1) Dans les conditions expérimentales de MERARG, aucune fagmentation significative du combustible n’est observée à des températures inférieures à 1000°C. 2) Le niveau de relâchement de gaz de fission entre 600°C et 800°C semble augmenter avec le temps d’entreposage du combustible.Le premier point indique que la fragmentation du combustible n’est pas une condition nécessaire au relâchement de gaz de fission dans cette gamme de température : d’autres mécanismes peuvent être à l’origine de ce relâchement. Durant l’entreposage, le combustible est soumis principalement à l’auto-irradiation α. Celle-ci a pour effet de créer des défauts dans une zone qui n’en contenait initialement pas. Nous avons démontré que la cinétique du relâchement de gaz de fission entre 600°C et 800°C est concomitante avec la cinétique de recuit de défauts d’autoirradiation α. De plus, une cinétique auto-catalytique de germination-croissance de nano-clusters de gaz a été développée et confrontée aux résultats expérimentaux. En outre, une étude sur matériaux simulants démontre que, sur des pastilles d’UO2 frittées et implantées en xénon, une irradiation en régime électronique a pour effet d’accroitre le relâchement entre 600°C et 800°C. La littérature décrit la remise en solution des bulles de gaz de fission sous l’effet d’une irradiation de ce type. De plus, lors de leur remise en solution, les gaz de fission s’insèrent dans les défauts de la structure cristalline. Lors d’un traitement thermique, le recuit des défauts entraine la mobilité des atomes de gaz de fission insérés de ces mêmes défauts. Par germination-croissance, les paires gaz/défauts rejoignent un chemin de sortie, les gaz de fission sont donc relâchés.Ce travail a donc permis de retenir l’hypothèse d’un mécanisme de relâchement de gaz de fission entre 600°C et 800°C par recuit de défauts sans fragmentation significative du combustible. / The subject of this thesis concerns the evaluation of the source term (fission gas release) in incidental situations of type LOCA (Loss of Coolant Accident) of nuclear fuels. During such thermal transients, the fission gas release is characterized by successive bursts : the first one occurring between 600 and 800°C, and a second one at about 1100°C. This work is about the first burst release. It appear that this one come from the centre of the fuel pellet. The aim of this thesis is to study the mechanisms responsible for the fission gas release between 600°C and 800°C.To this purpose, we collected more than 200 results of thermal treatments carried out using the experimental platform MERARG. The analysis of this database reveals two important results : under the experimental conditions of MERARG, no significant fragmentation of the fuel was observed at temperatures below 1000°C ; the amount of fission gas release between 600°C and 800°C appears to increase with fuel storage time.The first result suggests the fragmentation of the fuel is not a necessary condition for the release of fission gas in this temperature range. Other mechanisms may then be responsible for this gas release. During its storage, the fuel undergoes α particle self-irradiation. We demonstrate that the kinetics of fission gas release between 600°C and 800°C is simultaneous with the kinetics of the annealing of self-irradiation defects at this same temperature. The mechanism involves an autocatalytic process leading to a kinetic of fast germination-growth of gas nano-clusters. This model perfectly explains the experimental results in the database. To confirm this mechanism, a study on surrogate materials demonstrates that, in UO2 pellets sintered and implanted by Xe, irradiations in the electronic regime actually promote the release of implanted Xe at those temperatures. The re-dissolution of the fission gas bubbles by this kind of irradiation is consistent with observations in other contexts. Those conclusions allow to extend the mechanism for release to irradiated fuel.During the storage of the fuel, α self-irradiation promotes the re-dissolution of the trapped gas. The consequences of this effect are particularly important in the region close to the grain boundaries, where the concentration of defects is also larger. The irradiation mechanism increases the fraction of fission gas available for release, depleting the amount of gas initially trapped in bubbles. The gas in solution can effectively be carried by crystal defects, largely available in the irradiated fuel and whose migration at 600-800°C induces the mobility of the fission gas. When they reach an outlet path, the gas can be released from the pellet in a way consistent with the model of autocatalytic germination-growth we developed to explain the macroscopic results of the database.In conclusion, this work supports the hypothesis of a mechanism of fission gas release in the range 600-800°C via a mechanism involving the migration and annealing of defects without significant fragmentation of the fuel.

Les caractéristiques de l'offre de gaz en Europe et les spécificités du marché gazier ont conduit les régulateurs à adopter des régulations asymétriques, prenant la forme de gas release et d'objectifs de pertes de parts de marché. Les expériences empiriques montrent, en accord avec la théorie économique, que ces mesures rendent des concurrents actifs sur le marché et ne découragent pas les investissements. En terme de concurrence, les effets sont plus mitigés. Certains effets positifs trouvent certainement leur cause dans la croissance de la consommation qui est parfois exponentielle ou le développement des infrastructures d'importation et de transport. Ces mesures peuvent cependant favoriser les comportements collusifs, les stratégies d'écrémage ou de « reverse cherry picking », ainsi que des entrées inefficaces, rendues possibles car le concurrent est protégé pour une période de temps donnée. Un gas release crée une relation commerciale entre l'opérateur historique et son concurrent, ainsi qu'un système de contraintes sur les capacités de chacun. Les stratégies de prix ou de quantités sont alors modifiées. Les prix d'équilibre sont plus volatils et peuvent s'éloigner nettement du « mark-u p » de concurrence. De même, les stratégies d'un modèle de COURNOT se complexifient. L'opérateur historique, si les quantités rétrocédées sont fortes et ses approvisionnements faibles, peut laisser augmenter volontairement ses coûts pour accroître ses profits. Cette stratégie d'augmentation des coûts des rivaux est d'autant plus possible que le prix de rétrocession est proche de ses coûts d'approvisionnement. Elle ne détériore pas le surplus des consommateurs mais diminue le bien-être. Le régulateur peut restaurer l'incitation à l'efficacité en fixant une proportion rétrocédée en fonction du niveau des approvisionnements observé. Cette proportion ne doit pas être trop faible pour faire bénéficier le marché de l'incitation à l'efficacité de l'opérateur historique et des ventes plus importantes des deux opérateurs. Dans un même temps, une proportion trop élevée accentue les possibilités d'augmentation des coûts des rivaux ou de collusion.

<p>Presently there is a clear trend of increasing demands on in-pile performance of nuclear fuel. Higher target burnups, part length rods and various fuel additives are some examples of this trend. Together with an increasing demand from the public for even safer nuclear power utilisation, this implies an increased focus on various experimental, preferably non-destructive, methods to characterise the fuel.</p><p>This thesis focuses on the development and experimental evaluation of such methods. In its first part, the thesis presents a method based on gamma-ray spectroscopy with germanium detectors that have been used at various power reactors in Europe. The aim with these measurements is to provide information about the thermal power distribution within fuel assemblies in order to validate core physics production codes. The early closure of the Barsebäck 1 BWR offered a unique opportunity to perform such validations before complete depletion of burnable absorbers in Gd-rods had taken place. To facilitate the measurements, a completely submersible measuring system, LOKET, was developed allowing for convenient in-pool measurements to be performed.</p><p>In its second part, the thesis describes methods that utilise in-pile measurements. These methods have been used in the Halden test-reactor for determination of fission gas release, pellet-cladding interaction studies and fuel development studies.</p><p>Apart from the power measurements, the LOKET device has been used for fission gas release (FGR) measurements on single fuel rods. The significant reduction in fission gas release in the modern fuel designs, in comparison with older designs, has been demonstrated in a series of experiments. A FGR database covering a wide range of burnup, power histories and fuel designs has been compiled and used for fuel performance analysis. The fission gas release has been measured on fuel rods with average burnups well above 60 MWd/kgU. The comparison between core physics calculations (PHOENIX-4/POLCA-7) and the in-pool measurements of thermal power indicates that the nodal power can generally be predicted with an accuracy within 4% and the bundle power with an accuracy better than 2%, expressed as rms errors.</p><p>In-pile experiments have successfully simulated the conditions that occur in a fuel rod following a primary debris failure, being secondary fuel degradation. It was concluded that massive hydrogen pick-up takes place during the first few days following the primary failure and that a pre-oxidized layer does not function as a barrier towards hydriding in an environment with a very high partial pressure of hydrogen. Another series of in-pile experiments clearly indicate that increased UO₂ grain size is an effective way of suppressing fission gas release in LWR fuel up to the burnup level covered (55 MWd/kgUO₂).</p>

Presently there is a clear trend of increasing demands on in-pile performance of nuclear fuel. Higher target burnups, part length rods and various fuel additives are some examples of this trend. Together with an increasing demand from the public for even safer nuclear power utilisation, this implies an increased focus on various experimental, preferably non-destructive, methods to characterise the fuel. This thesis focuses on the development and experimental evaluation of such methods. In its first part, the thesis presents a method based on gamma-ray spectroscopy with germanium detectors that have been used at various power reactors in Europe. The aim with these measurements is to provide information about the thermal power distribution within fuel assemblies in order to validate core physics production codes. The early closure of the Barsebäck 1 BWR offered a unique opportunity to perform such validations before complete depletion of burnable absorbers in Gd-rods had taken place. To facilitate the measurements, a completely submersible measuring system, LOKET, was developed allowing for convenient in-pool measurements to be performed. In its second part, the thesis describes methods that utilise in-pile measurements. These methods have been used in the Halden test-reactor for determination of fission gas release, pellet-cladding interaction studies and fuel development studies. Apart from the power measurements, the LOKET device has been used for fission gas release (FGR) measurements on single fuel rods. The significant reduction in fission gas release in the modern fuel designs, in comparison with older designs, has been demonstrated in a series of experiments. A FGR database covering a wide range of burnup, power histories and fuel designs has been compiled and used for fuel performance analysis. The fission gas release has been measured on fuel rods with average burnups well above 60 MWd/kgU. The comparison between core physics calculations (PHOENIX-4/POLCA-7) and the in-pool measurements of thermal power indicates that the nodal power can generally be predicted with an accuracy within 4% and the bundle power with an accuracy better than 2%, expressed as rms errors. In-pile experiments have successfully simulated the conditions that occur in a fuel rod following a primary debris failure, being secondary fuel degradation. It was concluded that massive hydrogen pick-up takes place during the first few days following the primary failure and that a pre-oxidized layer does not function as a barrier towards hydriding in an environment with a very high partial pressure of hydrogen. Another series of in-pile experiments clearly indicate that increased UO2 grain size is an effective way of suppressing fission gas release in LWR fuel up to the burnup level covered (55 MWd/kgUO2).

Le liner métallique à confiner le matériau combustible des plaques GenIV doit, pour tenir son rôle, supporter « l'agression » des flux de neutrons rapides et d’impuretés implantées (produits de fission, hélium). Le travail de thèse présenté a contribué à la compréhension des mécanismes de fragilisation dans les métaux sous irradiation : il propose un modèle pour la nucléation et la croissance de bulles de gaz tels que l’hélium. L’approche utilisée couple une démarche de modélisation à une démarche expérimentale. Des mesures de relâchement obtenues par les techniques de spectrométrie de masse (TDS) et d’analyse par la réaction nucléaire (NRA) ainsi que des caractérisations par microscopie électronique en transmission (MET) ont été réalisées. Le développement d’un modèle simplifié de dynamique d’amas a permis d’interpréter le couplage entre la dynamique de relâchement de l’hélium et celle des bulles. Ce modèle a permis d’une part, de simuler les expériences d’implantation/récuit à partir d’un jeu de grandeurs physiques cohérentes avec celle de la littérature, et d’autre part, de mettre en évidence un couplage fort entre les concentrations des espèces libres (atomes d’hélium et lacunes) et la composition moyenne des bulles. Les dynamiques singulières de relâchement du gaz observées expérimentalement ont pu être expliquées par le mûrissement d’une population de bulles, initialement « surpressurisées », qui poursuivent leur croissance en réduisant leur concentration totale et leur pression / The metal liner dedicated to continue the fuel assembly of the Gas Fast Reactor, is intended to resist to a fast neutron flux and the implantation of impurities such as helium and the fission products. This PhD work contributes to the understanding of one of the mechanisms inducing the metal embrittlement under irradiation; it deals with a model that predicts the nucleation and growth of gas bubbles, such as helium, into a metal. The approach of the thesis relies on both theoretical and experimental works. The gas release measurements have been performed with the Nuclear Reaction Analysis (NRA) method and the Thermal Desorption Spectrometry (TDS); the bubbles characterization performed by Transmission Electronic Microscopy (TEM). The development of a simple model for the description of the cluster dynamic (clusters composed by defects and gas atoms) proposes some explanations for the coupling between the dynamics of the helium release and the bubbles evolution. This model enables to simulate the implantation experiments and the following annealing sequences, with a relevant physical dataset and coherent with the literature. Moreover it enhances the strong inference between the species concentration into the bulk (vacancies and helium atoms) and the mean composition of the bubbles. The peculiar dynamics of the gas release observed during the experiments, initially rapid and then significantly reduced , would be due to the ripening of the bubbles, pressurized after the room temperature implantation, which keep on growing and reducing their concentration and internal pressure

The aim of this master thesis is to show a connection among nuclear fuel safety, experiments led in research reactors and calculation codes. This thesis focuses on the calculation code Transuranus. There are represented four experiments, which were calculated in Transuranus. The fission gas release, elongation and growth of fuel were particularly monitored. Is is possible to set differences among versions v1m1j09 and v1m3j12 from achieved results, as well as the influence of selected Transuranus parameters on the results, so the thesis may bring new pieces of knowledge for improvement of safety analysis calculation by Transuranus.