Sökning: "Lead-bismuth-eutectic"
Visar resultat 1 - 5 av 8 avhandlingar innehållade ordet Lead-bismuth-eutectic.
1. Prediction of forced convection heat transfer to Lead-Bismuth-Eutectic
Sammanfattning : The goal of this work is to investigate the capabilities of two different commercial codes, OpenFOAM and ANSYS CFX, to predict forced convection heat transfer in low Prandtl number fluids and investigate the sensitivity of these predictions to the type of code and to several input parameters.The goal of the work is accomplished by predicting forced convection heat transfer in two different experimental setups with the codes OpenFOAM and ANSYS CFX using three different turbulence models and varying the input parameters in an extensive sensitivity analysis. LÄS MER
2. Why Faster is Better : On Minor Actinide Transmutation in Hard Neutron
Sammanfattning : In this thesis, options for efficient transmutation of transuranium elements are discussed. The focus is on plutonium, americium and curium mainly because of their long-term contribution to the radiotoxicity of spent nuclear fuel. Two innovative helium-cooled core designs are proposed, dedicated to the transmutation of actinides. LÄS MER
3. Neutronic and burnup studies of accelerator-driven systems dedicated to nuclear waste transmutation
Sammanfattning : Partitioning and transmutation of plutonium, americium, and curium is inevitable if the radiotoxic inventory of spent nuclear fuel is to be reduced by more than a factor of 100. But, admixing minor actinides into the fuel severely degrades system safety parameters, particularly coolant void reactivity, Doppler effect, and (effective) delayed neutron fractions. LÄS MER
4. Transmutation of Americium in Fast Neutron Facilities
Sammanfattning : In this thesis, the feasibility to use a medium sized sodium cooled fast reactor fully loaded with MOX fuel for efficient transmutation of americium is investigated by simulating the safety performance of a BN600-type fast reactor loaded with different fractions of americium in the fuel, using the safety parameters obtained with the SERPENT Monte Carlo code. The focus is on americium mainly due to its long-term contribution to the radiotoxicity of spent nuclear fuel and its deterioration on core's safety parameters. LÄS MER
5. Coil Design for a Mirror Based Fusion-Fission Reactor
Sammanfattning : The SFLM Hybrid project aims to show that it is probable that a fusion-fission reactor can be constructed with a single-cell minimum B mirror machine as a neutron source. In this licentiate thesis, theoretical work has been done with the magnetic coil system of such a device and also with the overall concept. LÄS MER