Sökning: "irradiated nuclear fuel"
Visar resultat 11 - 15 av 20 avhandlingar innehållade orden irradiated nuclear fuel.
11. Nuclear safeguards evaluation and analysis techniques for application to nuclear fuel material in Generation IV nuclear energy systems
Sammanfattning : A new generation of nuclear energy systems called Generation IV is under development to ensure that nuclear power will be a safe, reliable and sustainable energy source for the future. This thesis addresses the challenge of making future nuclear energy systems increasingly resistant to nuclear material diversion attempts. LÄS MER
12. Stability of Alternative Nuclear Fuel Materials in Aqueous Systems
Sammanfattning : Nuclear power produces a large portion of the electricity worldwide. It has been the largest low-carbon energy source for more than 30 years and has played an essential role in the security of energy supplies for many countries. LÄS MER
13. Influence of metallic fission products and self irradiation on the rate of spent nuclear fuel-matrix dissolution
Sammanfattning : Denna licentiatavhandling behandlar effekten av två inneboende egenskaper (fissions produkter och egenbestrålning) hos utbränt kärnbränsle på hastigheten för strålningsinducerad upplösning av bränslematris (UO2). I ett framtida djupförvar kommer det utbrända kärnbränslet att deponeras 500 meter ner i berggrunden i en reducerande miljö. LÄS MER
14. 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
15. Delayed Hydride Cracking in Irradiated Zircaloy
Sammanfattning : Under some circumstances nuclear fuel cladding tubes made from zirconium based alloys may develop long axial cracks. The formation of these cracks is mainly thought to be connected with the oxiditian and hydriding of the cladding which takes plage after the the formation of a small primary defect. LÄS MER