Sökning: "oxidative dissolution"
Visar resultat 11 - 15 av 25 avhandlingar innehållade orden oxidative dissolution.
11. Redox Chemistry in Radiation Induced Dissolution of Spent Nuclear Fuel : from Elementary Reactions to Predictive Modeling
Sammanfattning : The focus of this doctoral thesis is the redox chemistry involved in radiation induced oxidative dissolution of spent nuclear fuel and UO2 (as a model substance for spent nuclear fuel). It is shown that two electron oxidants are more efficient than one electron oxidants in oxidative dissolution of UO2 at low oxidant concentrations. LÄS MER
12. Formation and Decomposition of Platinum–Thallium Bond, Kinetics and Mechanism. Structural Characterization of Some Metal Cyanides in the Solid State
Sammanfattning : The kinetic and mechanistic features of a new series ofplatinum-thallium cyano compounds containing a direct andunsupported by ligands metal-metal bond have been studied insolution, using standard mixandmeasurespectrophotometric technique and stoppedflow method.These reactions are interpreted as oxidative addition of the cspecies to the square planar Pt(CN)42-complex. LÄS MER
13. Toxicity and biocompatibility of nanoparticles, and studies on oxidative stress and DNA damage
Sammanfattning : Oxidative stress is associated with several diseases, either as a cause or a consequence. Chronic kidney disease (CKD) is one example of a disease in which elevated levels of oxidative stress are frequently reported. LÄS MER
14. The interaction of dissolved hydrogen with α-radiolytic oxidants during nuclear fuel dissolution
Sammanfattning : Used nuclear fuel contains radiotoxic elements that will need to be kept isolated from the biosphere over a time period of 100 000 years. The KBS-3 geological storage concept aims to prevent the migration of radionuclides into the environment by different engineered barriers. LÄS MER
15. The effect of solid state inclusions on the reactivity of UO2 : A kinetic and mechanistic study
Sammanfattning : The release of radionuclides is a key process in the safety assessment of a deep geological repository for spent nuclear fuel. A large fraction of the release is assumed to be a consequence of dissolution of the fuel matrix, UO2. In this doctoral thesis, the kinetics and the mechanisms behind oxidative U(IV) dissolution were studied. LÄS MER