934 resultados para Radioactive waste vitrification
Resumo:
Retrieval, treatment, and disposal of high-level radioactive waste (HLW) is expected to cost between 100 and 300 billion dollars. The risk to workers, public health, and the environment are also a major area of concern for HLW. Visualization of the interface between settled solids and the optically opaque liquid is needed for retrieval of the waste from underground storage tanks. A Profiling sonar selected for this research generates 2-D image of the interface. Multiple experiments were performed to demonstrate the effectiveness of sonar in real-time monitoring the interface inside HLW tanks. First set of experiments demonstrated that objects shapes could be identified even when 30% of solids entrained in liquid, thereby mapping the interface. Simulation of sonar system validated these results. Second set of experiments confirmed the sonar’s ability in detecting the solids with density similar to the immersed liquid. Third set of experiments determined the affects of near by objects on image resolution. Final set of experiments proved the functional and chemical capabilities of sonar in caustic solution.
The potential of coconut fibers in raw and treated forms to remove sup(241)Am from aqueous solutions
Resumo:
Der Plan, große Mengen radioaktiver Materialien in Salinar- gesteine von Salzstöcken einzulagern, schließt die Rück- holbarkeit praktisch aus. Bei der Abschätzung des Langzeitverhaltens der Gesteine, der Grubenbaue und des gesamten Diapirs sind - wie auch beim Einlagerungsvorgang selbst - Fehler nicht auszuschließen und nicht korrigierbar. Die Antragsteller behandeln die geowissenschaftlichen Aspekte der Einlagerung (Teilprojekt 6) nicht qualifiziert und widmen den damit verbundenen Problemen eine unangemessen geringe Aufmerksamkeit. Sie lassen die einem solchen Projekt adäquate planerische Sorgfalt vermissen, gehen mit den zur Verfügung stehenden Daten in ihrer Argumentation ungenau oder selektiv um und erwecken den Eindruck, unter der Erdoberfläche nach dem 'trial-and-error'-Prinzip Vorgehen zu wollen. Salzstöcke sind tektonisch grundsätzlich instabile Gesteinskörper. Die an ihrem Aufbau überwiegend beteiligten Gesteine sind die wasserlöslichsten der Erdkruste; sie reagieren am empfindlichsten auf mechanische und thermische Beanspruchung und sind am reaktionsfähigsten bei möglichen Interaktionen zwischen Einlagerungsmaterial und Einlagerungsmedium. Salzstöcke sind die auf bergtechnische Eingriffe am sensibelsten reagierenden Gesteinskörper, insbesondere, wenn der am Salzspiegel herrschende Lösungszustand gestört wird, wenn durch künstliche Hohlräume im Innern Kriechbewegung (Konvergenz) des gesamten Salinars ausgelöst wird und wenn mit der Einlagerung thermische Belastungen einhergehen, welche höher sind als die mit der Gesteinsbildung und -Umbildung verbundenen Temperaturen es jemals waren. Daß trotz dieser Empfindlichkeit Gewinnungsbergbau in Diapiren möglich ist, ist kein Beleg für ihre Eignung als Endlager. Die Geowissenschaften verfügen über Modellvorstellungen zur Deutung der Salinargenese, des Salzaufstiegs und des gebirgsmechanischen Verhaltens. Diese Modelle sind teils als 'Lehrbuchwahrheit1 allgemein akzeptiert, werden z.T. aber auch als Hypothesen kontrovers diskutiert. Langzeitprognosen über das Verhalten von Gesteinen sind nicht verläßlich, wenn sie auf widersprochenen Modellvorstellungen über das Wesen von Gesteinen und Gesteinsverhalten beruhen. Die Salzstockauswahl ging der geowissenschaftlichen Erkundung voraus. Die wenigen publizierten Daten zur regionalen Geologie lassen nicht auf einen bergbautechnisch besonders leicht zu beherrschenden Salzstock schließen. Die Lage des Diapirs im Verbreitungsgebiet wasserreicher quartärzeitlicher Rinnensysteme spricht genauso gegen die Standortwahl wie die zu erwartende komplizierte Interntektonik und die politisch bedingte Unerforschbarkeit der Gesamtstruktur Gorleben-Rambow. Als Fehlentscheidung ist die durch Landkäufe am Standort Gorleben vorweggenommene Auswahl des Fabrikgeländes einschließlich Schachtanlage und Tritiumwasser-Verpressung auf dem Salzstock zu werten. Der nicht auszuschließende "Störfall Wassereinbruch" kann sich über Tage auf die Standsicherheit der riesigen Gebäude und Lagerbecken zerstörerisch auswirken und so Kontamination der Umgebung verursachen. Geowissenschaftliche Gründe, Erfahrungen aus der Bergbaukunde und die Erwartung, daß man fehlerhaftes Handeln nicht ausschließen kann, führen den Verfasser zu der Überzeugung, daß die Endlagerung radioaktiver Abfälle im Salz nicht zu empfehlen und nicht zu verantworten ist.
Resumo:
The Gorleben salt dome is actually investigated for its suitability as a repository for radioactive waste. It is crossed by a subglacial drainage channel, formed during the Elsterian glaciation (Gorleben channel). Some units of its filling vary strongly in niveau and thickness. Lowest positions and/or largest thickness are found above the salt dome. This is interpreted as a result of subrosion during the Saalean glaciation. The rate can be calculated from niveau differences of sediments formed during the Holsteinian interglacial. However, their position might have been influenced by other factors also (relief of the channel bottom, glacial tectonics, settlement of underlying clay-rich sediments). Their relevance was estimated applying statistical techniques to niveau and thickness data from 79 drillings in the Gorleben channel. Two classes of drillings with features caused by either Saalean subrosion or sedimentary processes during the filling of the Gorleben channel can be distinguished by means of factor and discriminant analysis. This interpretation is supported by the results of classwise correlation and regression analysis. Effects of glacial tectonics on the position of Holsteinian sediments cannot be misunderstood as subrosional. The influence of the settlement of underlying clay sediments can be estimated quantitatively. Saalean subrosion rates calculated from niveau differences of Holsteinian sediments between both classes differ with respect to the method applied: maximum values are 0,83 or 0,96 mm/a, average values are 0,31 or 0,41 mm/a.
Resumo:
Any safety assessment of a permanent repository for radioactive waste has to include an analysis of the geomechanical stability of the repository and integrity of the geological barrier. Such an analysis is based on geological and engineering geological studies of the site, on laboratory and in-situ experiments, and on numerical calculations. Central part of the safety analysis is the geomechanical modelling of the host rock. The model should simulate as closely as possible the conditions at the site and the behaviour of the rock (e.g., geology, repository geometry, initial rock stress, and constitutive models). On the basis of the geomechanical model numerical calculations are carried out using the finite-element method and an appropriate discretization of the repository and the host rock. The assessment of the repository stability and the barrier integrity is based on calculated stress and deformation and on the behaviour of the host rock measured and observed in situ. An example of the geomechanical analysis of the stability and integrity of the Bartensieben mine, a former salt mine, is presented. This mine is actually used as a repository for low level radioactive waste. The example includes all necessary steps of geological, engineering geological, and geotechnical investigations.
Resumo:
Harnessing the power of nuclear reactions has brought huge benefits in terms of nuclear energy, medicine and defence as well as risks including the management of nuclear wastes. One of the main issues for radioactive waste management is liquid radioactive waste (LRW). Different methods have been applied to remediate LRW, thereunder ion exchange and adsorption. Comparative studies have demonstrated that Na2Ti2O3SiO4·2H2O titanosilicate sorption materials are the most promising in terms of Cs+ and Sr2+ retention from LRW. Therefore these TiSi materials became the object of this study. The recently developed in Ukraine sol-gel method of synthesizing these materials was chosen among the other reported approaches since it allows obtaining the TiSi materials in the form of particles with size ≥ 4mm. utilizing inexpensive and bulk stable inorganic precursors and yielded the materials with desirable properties by alteration of the comparatively mild synthesis conditions. The main aim of this study was to investigate the physico-chemical properties of sol-gel synthesized titanosilicates for radionuclide uptake from aqueous solutions. The effect of synthesis conditions on the structural and sorption parameters of TiSi xerogels was planned to determine in order to obtain a highly efficient sorption material. The ability of the obtained TiSis to retain Cs+, Sr2+ and other potentially toxic metal cations from the synthetic and real aqueous solutions was intended to assess. To our expectations, abovementioned studies will illustrate the efficiency and profitability of the chosen synthesis approach, synthesis conditions and the obtained materials. X-ray diffraction, low temperature adsorption/desorption surface area analysis, X-ray photoelectron spectroscopy, infrared spectroscopy and scanning electron microscopy with energy dispersive X-ray spectroscopy was used for xerogels characterization. The sorption capability of the synthesized TiSi gels was studied as a function of pH, adsorbent mass, initial concentration of target ion, contact time, temperature, composition and concentration of the background solution. It was found that the applied sol-gel approach yielded materials with a poorly crystalline sodium titanosilicate structure under relatively mild synthesis conditions. The temperature of HTT has the strongest influence on the structure of the materials and consequently was concluded to be the control factor for the preparation of gels with the desired properties. The obtained materials proved to be effective and selective for both Sr2+ and Cs+ decontamination from synthetic and real aqueous solutions like drinking, ground, sea and mine waters, blood plasma and liquid radioactive wastes.