Sökning: "chemical safety assessment"
Visar resultat 16 - 20 av 42 avhandlingar innehållade orden chemical safety assessment.
16. Retardation of Tracers in Crystalline Rock Sorption and Matrix Diffusion of Alkali Metal and Alkaline Earth Metal Tracers in Laboratory and Field Experiments
Sammanfattning : The safety of geological repositories for radioactive or environmentally hazardous waste is dependent on several engineered and natural barriers. One of the natural barriers is the surrounding bedrock, in which water-conducting rock fractures may act as transport pathways in the event of a leakage from the engineered barriers. LÄS MER
17. The Bentonite Barrier - Swelling Properties, Redox Chemistry and Mineral Evolution
Sammanfattning : Bentonite is planned for use as a buffer material in high-level radioactive waste repositories, where safety assessment is performed for very long periods (100-1000 ka). This thesis focuses on the swelling of smectites in liquid water, and analysis of bentonite from field experiments at Äspö Hard Rock Laboratory, Sweden. LÄS MER
18. Water density impact on water flow and mass transport in rock fractures
Sammanfattning : One way of taking care of spent nuclear fuel is to place it in a geological repository. In Sweden, a three-barrier system is planned. The system is based on encapsulating the fuel in copper canisters. These are surrounded by bentonite clay and buried under 500 m of bedrock. LÄS MER
19. Long-term Performance of PVC and CSPE Cables used in Nuclear Power Plants : the Effect of Degradation and Plasticizer migration
Sammanfattning : Enormous amounts of low voltage cables installed in a Swedish nuclear power plant are reaching their expected lifetimes. Since the cables are crucial to operational safety, it is of great importance that the actual condition of the installed cables is determined. LÄS MER
20. Effects of HCO3- and ionic strength on the oxidation and dissolution of UO2
Sammanfattning : The kinetics for radiation induced dissolution of spent nuclear fuel is a key issue in the safety assessment of a future deep repository. Spent nuclear fuel mainly consists of UO2 and therefore the release of radionuclides (fission products and actinides) is assumed to be governed by the oxidation and subsequent dissolution of the UO2 matrix. LÄS MER