Essays about: "LFR"
Found 5 essays containing the word LFR.
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1. Effect of Proton Irradiation on the Mechanical Properties of Fe-10Cr-4Al in Liquid Lead
University essay from KTH/FysikAbstract : Among the structural materials under consideration for future lead-cooled fastreactors, special attention is paid to ferritic Fe-10Cr-4Al due to its superior corrosionand erosion protective properties, as well as its insensitivity to liquid metalembrittlement in liquid lead. This thesis gives an inside look into the radiation damageproperties of the alloy and the possible embrittlement scenarios. READ MORE
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2. Uncertainty & Sensitivity Analysis of Nuclear Fuel Using Transuranus & Dakota
University essay from KTH/FysikAbstract : With the initiative taken by the SUNRISE project (Sustainable Nuclear Energy Research in Sweden) to construct a Lead-cooled research reactor, this thesis intends to extend the knowledge within nuclear fuel development. By using integral iterative modelling and simulating techniques that mimic real-world phenomena, novel fuel materials like uranium nitride are assessed for future validation. READ MORE
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3. An investigation of fuel cycles and material flows for a lead-cooled fast reactor using the Monte Carlo code Serpent
University essay from Tillämpad kärnfysikAbstract : The Monte Carlo code Serpent has been used to model the material flows andisotope compositions for a lead cooled fast reactor. The demonstration sized trainingreactor ELECTRA was chosen for the investigation, and different fuel cycle scenarioswere studied. READ MORE
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4. CONQUER CORROSION : Key issues of the lead-cooled fast reactor design
University essay from Tillämpad kärnfysikAbstract : The lead-cooled fast reactor (LFR) is one of the concepts of the Generation IV reactorsystems. There are some issues that have to be solved before a research orcommercial LFR can be built. READ MORE
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5. Application of CFD to Safety and Thermal-Hydraulic Analysis of Lead-Cooled Systems
University essay from KTH/FysikAbstract : Computational Fluid Dynamics (CFD) is increasingly being used in nuclear reactor safety analysis as a tool that enables safety related physical phenomena occurring in the reactor coolant system to be described in more detail and accuracy. Validation is a necessary step in improving predictive capability of a computationa code or coupled computational codes. READ MORE