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Es wird ein historischer Überblick über die seit Ende der 1950er Jahren betrachteten Optionen zum Umgang mit flüssigen hochradioaktiven Abfällen vorgestellt. Ausgehend von den Randbedingungen der Wiederaufarbeitung von abgebrannten Kernbrennstoffen werden mögliche Verfahren und Strategien zur Verfestigung dieser Abfälle zusammengefasst und die Entscheidungsprozesse in Deutschland diskutiert. A historical overview of the options for solidification of liquid highly radioactive wastes is presented, which has been developed since the end of the 1950s. Starting from the boundary conditions of the reprocessing of spent nuclear fuel, possible methods and strategies for solidification of this wastes are summarized and the decision-making processes in Germany are discussed.
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The current state of knowledge of central aspects of radioactive waste repository research was presented in the course of the DAEF conference "Key topics in deep geological disposal". For the first time socio-economic and socio-technical issues played an important role within a conference focusing on the disposal of radioactive waste. Scientists from about 16 different countries presented their scientific work in 8 sessions and during a poster session.
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Methane. --- Methane --- wastes --- wastes --- Fermentation --- Fermentation
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Hazardous wastes --- Hazardous wastes --- Management --- Congresses --- Management --- Congresses
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Since 1967 radioactive wastes have been disposed of in the Asse II salt mine in Northern Germany. A signifi-cant part of these wastes originated from the pilot reprocessing plant WAK in Karlsruhe and consisted of cemented NaNO3 solutions bearing fission products, actinides, as well as process chemicals. With respect to the long-term behavior of these wastes, the licensing authorities requested leaching experiments with full scale samples in relevant salt solutions which were performed since 1979. The experiments aimed at demonstrating the transferability of results obtained with laboratory samples to real waste forms and at the investigation of the effects of the industrial cementation process on the properties of the waste forms. This research program lasted until 2013. The corroding salt solutions were sampled several times and after termination of the experiments, the solid materials were analyzed by various methods. The results present-ed in this report cover the evolution of the solutions and the chemical and mineralogical characterization of the solids including radionuclides and waste components, and the paragenesis of solid phases (corrosion products). The outcome is compared to the results of model calculations. For safety analysis, conclusions are drawn on radionuclide retention, evolution of the geochemical environment, evolution of the density of solutions, and effects of temperature and porosity of the cement waste simulates on cesium mobilization.
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Ausgehend von den politischen und gesellschaftlichen Randbedingungen werden die Forschungs- und Entwicklungsarbeiten zur sicheren Endlagerung radioaktiver Abfälle, wie sie im Kernforschungszentrum Karlsruhe im Institut für Nukleare Entsorgung durchgeführt wurden, zusammengestellt. Die Organisationformen und die jeweils wesentlichen Forschungsthemen werden genannt sowie die gegenwärtigen Forschungsthemen und die Einbindung des Instituts in Lehre und Ausbildung und in Beratungsaufgaben. Research and development for safe disposal of radioactive wastes at the Nuclear Research Center Karlsruhe in the Institute of Nuclear Waste Disposal is presented. The political and societal boundary conditions for this R&D are referred to. The past organizational forms and the most important research topics are addresses as well as the current research topics including the involvement of the institute in training and education or consultation services.
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