Sökning: "Kärnkemi"
Visar resultat 6 - 10 av 12 avhandlingar innehållade ordet Kärnkemi.
6. 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
7. Understanding the mechanisms behind atom transfer radical polymerization : exploring the limit of control
Sammanfattning : Atom transfer radical polymerization (ATRP) is one of the most commonly employed techniques for controlled radical polymerization. ATRP has great potential for the development of new materials due to the ability to control molecular weight and polymer architecture. LÄS MER
8. The inter-and intramolecular selectivity of the carbonate radical anion in its reactions with lignin and carbohydrates
Sammanfattning : In the present thesis, the effects of the carbonate radical anion on lignin and cellulose were investigated. The carbonate radical has a rather high reactivity towards aromatic lignin constituents. It reacts especially fast with phenolates. All these reactions occur by way of electron transfer. LÄS MER
9. Radiation induced dissolution of model compounds for spent nuclear fuel : mechanistic understanding of oxidative dissolution and its inhibition
Sammanfattning : This doctoral thesis is focused on radiation induced oxidative dissolution of UO2, Pd-doped UO2, SIMFUEL (as model substances for spent nuclear fuel) and UN (a possible future fuel) and inhibition of the oxidative dissolution. H2O2 is assumed to be the most important oxidant for spent nuclear fuel dissolution under deep repository conditions. LÄS MER
10. Generation, stability and migration of montmorillonite colloids in aqueous systems
Sammanfattning : In Sweden the encapsulated nuclear waste will be surrounded by compacted bentonite in the granitic host rock. In contact with water-bearing fractures the bentonite barrier may release montmorillonite colloids that may be further transported in groundwater. LÄS MER