Sökning: "zircaloy"
Hittade 5 uppsatser innehållade ordet zircaloy.
1. High spatial resolution study of local corrosion effects on BWR-fuel cladding : Using a combined method of GEANT4 and lwrChem
Uppsats för yrkesexamina på avancerad nivå, Uppsala universitet/Tillämpad kärnfysikSammanfattning : The core of a BWR constitutes a highly complex radiational and chemical environment. Nuclear fission is utilized to generate power and as a consequence, large quantities of ionizing radiation are produced. Gamma and beta-particles along with neutrons have the sufficient ranges to escape the fuel rods and deposit energy in the reactor coolant. LÄS MER
2. Qualification of a Physical Model of Cladding Creep During Dry Storage of Spent Nuclear Fuel
Master-uppsats, KTH/FysikSammanfattning : In dry interim storage of spent nuclear fuel, thermal creep is one of the major threats to the fuel cladding integrity due to the constant decay heat generation from the fission products and minor actinides in the fuel, and the increase in fuel rod internal pressure which is present after burnup. Plenty of research has been done on either empty cladding tubes irradiated in a research reactor, or on spent fuel that is defueled prior to the examination. LÄS MER
3. Extraction Replicas of Common Engineering Alloys for Analysis of Small Precipitates
Master-uppsats, KTH/MaterialvetenskapSammanfattning : Characterization of small precipitates is important for development of new alloys. One inherent difficulty in characterisation of small precipitates with electron microscopy techniques while the particles are embedded in the matrix, is that the surrounding bulk material will contribute to the analysed signal- limiting, for example, the quantification of the composition of particles. LÄS MER
4. Degradation mechanisms of UN and UN–10U3Si2 pellets of varying microstructure by comparative steam oxidation experiments
Master-uppsats, KTH/ReaktorfysikSammanfattning : During an extended LOCA in a LWR, the current UO2 fuel reaches very high temperatures and eventually melts, while the current Zircaloy fuel cladding oxidizes releasing hydrogen. These two consequences can lead to an unacceptable amount of radioactive release by presenting accident routes for containment failure. LÄS MER
5. Experimental evalution of oxide growth in binary zirconium alloys along with pure zirconium and Zircaloy-2 by steam corrosion testing
Master-uppsats, KTH/FysikSammanfattning : .... LÄS MER