Essays about: "Lead-bismuth eutectic"

Found 4 essays containing the words Lead-bismuth eutectic.

1. 1. SSRT of 10-4 FeCrAl in LBE and Pb to Characterize Liquid Metal Embrittlement Effects

   University essay from KTH/Fysik

   Author : Daniel Stein; [2022]
   Keywords : Liquid Metal Embrittlement; Lead; Bismuth; Lead-Bismuth Eutectic; Slow Strain Rate Testing;

   Abstract : 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

3. 2. CONQUER CORROSION : Key issues of the lead-cooled fast reactor design

   University essay from Tillämpad kärnfysik

   Author : Mathias Hareland; [2011]
   Keywords : Nuclear power; Generation-IV; lead cooled fast reactor; LFR; corrosion; MAXTHAL; MYRRHA; Lead-bismuth eutectic; LBE;

   Abstract : 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

4. 3. Application of CFD to Safety and Thermal-Hydraulic Analysis of Lead-Cooled Systems

   University essay from KTH/Fysik

   Author : Marti Jeltsov; [2011]
   Keywords : Coupled Codes; Verification Validation; CFD; System Thermal-Hydraulics; Lead Cooled sys-;

   Abstract : 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

5. 4. TRACE Analysis for Transient Thermal-hydraulics of A Heavy Liquid Metal Cooled System

   University essay from KTH/Kärnkraftssäkerhet

   Author : Yiqiong Shao; [2011]
   Keywords : ;

   Abstract : 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