Sökning: "Lead-Bismuth Eutectic"
Hittade 4 uppsatser innehållade orden Lead-Bismuth Eutectic.
1. SSRT of 10-4 FeCrAl in LBE and Pb to Characterize Liquid Metal Embrittlement Effects
Master-uppsats, KTH/FysikSammanfattning : 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. LÄS MER
2. CONQUER CORROSION : Key issues of the lead-cooled fast reactor design
Uppsats för yrkesexamina på avancerad nivå, Tillämpad kärnfysikSammanfattning : 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. LÄS MER
3. Application of CFD to Safety and Thermal-Hydraulic Analysis of Lead-Cooled Systems
Master-uppsats, KTH/FysikSammanfattning : 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. LÄS MER
4. TRACE Analysis for Transient Thermal-hydraulics of A Heavy Liquid Metal Cooled System
Master-uppsats, KTH/KärnkraftssäkerhetSammanfattning : 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. LÄS MER