Essays about: "LBE"
Found 5 essays containing the word LBE.
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1. SSRT of 10-4 FeCrAl in LBE and Pb to Characterize Liquid Metal Embrittlement Effects
University essay from KTH/FysikAbstract : In this work the susceptibility of Fe-10Cr-4Al steel to liquid metal embitterment (LME)in low oxygen environment was investigated. slow strain rate testing (SSRT) wereconducted on 10-4 FeCrAl steel in a stagnant lead from 340-480◦C, lead-bismutheutectic (LBE) from 140-450◦C and lead-bismuth mixture at 375◦C with increasingbismuth content from 0. READ MORE
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2. Optimisation of the bottom stirring praxis in a LD-LBE converter : Investigations and tests on phosphorous removal, nitrogen as stirring gas, and slopping
University essay from Uppsala universitet/Oorganisk kemiAbstract : The LD-process, called after the cities Linz and Donawitz, is used to convert pig iron into crude steel by blowing oxygen on top of the pig iron. A LD-LBE converter, Lance Bubbling Equilibrium, also stirs the melt trough a bottom stirring system. READ MORE
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3. 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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4. 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
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5. TRACE Analysis for Transient Thermal-hydraulics of A Heavy Liquid Metal Cooled System
University essay from KTH/KärnkraftssäkerhetAbstract : Heavy liquid metal (HLM - lead or lead bismuth eutectic) is considered as a candidate coolant for next-generation fast reactor and accelerate-driven systems (ADS), due to its favorable chemical, thermo-physical and neutronic properties in comparison with sodium which has been used as coolant in fast breeder reactors (FBRs). To perform design-base-accident analysis for the HLM-cooled reactors, the well-known transient thermal-hydraulic analysis codes (e. READ MORE